United States Nuclear Regulatory Commission - Protecting People and the Environment

Safety-Related (1) Motor-Operated Valve Testing and Surveillance Results of the Public Workshops (Generic Letter 89-10)

 June 28, 1989

TO:       ALL LICENSEES OF OPERATING NUCLEAR POWER PLANTS AND HOLDERS OF
          CONSTRUCTION PERMITS FOR NUCLEAR POWER PLANTS

SUBJECT:  SAFETY-RELATED (1) MOTOR-OPERATED VALVE TESTING AND SURVEILLANCE
          (GENERIC LETTER NO. 89-10) - 10 CFR 50.54(f)

BACKGROUND 

In Bulletin 85-03, dated November 15, 1985, and Supplement 1 of Bulletin 
85-03, dated April 27, 1988, the NRC recommended that licensees develop and 
implement a program to ensure that valve motor-operator switch settings 
(torque, torque bypass, position limit, overload) for motor-operated valves 
(MOVs) in several specified systems are selected, set, and maintained so that 
the MOVs will operate under design-basis (2) conditions for the life of the 
plant.  NRC staff assessments of the reliability of all safety-related MOVs, 
based on extrapolations of the currently available results of valve 
surveillances performed in response to Bulletin 85-03, indicate that the 
program to verify switch settings should be extended in order to ensure 
operability of all safety-related fluid systems.  The NRC staff's evaluation 
of the data indicates that, unless additional measures are taken, failure of 
safety-related MOVs and position-changeable MOVs (as defined under 
"Recommended Actions" of this generic letter) to operate under design-basis 
conditions will occur much more often than had previously been estimated.  

The ASME Code Section XI stroke-timing test for MOVs is performed to meet the 
inservice testing requirements of 10 CFR 50.55a(g).  Section XI testing for 
MOVs consists of stroking Class 1, 2, and 3 valves open and closed, usually 
without fluid pressure or flow in the lines, and measuring stroke time.  This 
Section XI testing is a useful tool and complements other tests used to verify 
MOV operability.  Variations in measured stroke times can be significant for 
DC-powered MOVs and can indicate valve degradation.  Additionally, periodic 
stroking of MOVs provides valve exercise and some measure of on-demand 
reliability.  


----------

(1)  The term "safety-related" refers to those systems and components that are 
relied on to remain functional during and following design-basis events to 
ensure (i) the integrity of the reactor coolant pressure boundary, (ii) the 
capability to shut down the reactor and maintain it in a safe shutdown con-
dition, and (iii) the capability to prevent or mitigate the consequences of 
accidents that could result in potential offsite exposures comparable to the 
guidelines of 10 CFR Part 100.

(2)  Design-basis events are defined as conditions of normal operation, 
including anticipated operational occurrences, design-basis accidents, 
external events, and natural phenomena for which the plant must be designed to 
ensure the functions delineated in foonote 1.  The design bases for each plant 
are those documented in pertinent licensee submittals such as the final safety 
analysis report.

8906290082
.                                       2                  June 28,1989

Section XI requires corrective action if a MOV does not exhibit its required 
change of disk position.  However, it is now recognized that the Section XI 
testing alone is not sufficient to provide assurance of MOV operability under 
design-basis conditions.  Assurance of design basis operability is necessary 
in order to meet the requirements in General Design Criteria 1, 4, 18, and 21 
of Appendix A to 10 CFR Part 50 and Criterion XI of Appendix B to 10 CFR 
Part 50.  

The design basis for certain normally open primary system MOVs (for example, 
those serving the reactor water cleanup system and the steam supply to 
high-pressure coolant injection and reactor core isolation cooling system 
turbines in boiling water reactors) demand that these MOVs close to isolate 
the largest postulated downstream pipe break outside the containment.  These 
MOVs are the subject of a full-scale blowdown flow testing program being 
conducted by Idaho National Engineering Laboratory (INEL) under NRC 
sponsorship as part of the resolution of Generic Issue 87, "Failure of HPCI 
Steam Line Without Isolation."  Preliminary test results (3) indicate that 
some MOVs may be subjected to mechanisms and loads that were not accounted for 
previously.  INEL's preliminary conclusions indicate that industry sizing 
equations for MOVs that must perform this type of safety-related function may 
not be conservative for all design-basis conditions.  The purpose of these 
tests is to confirm that these valves will operate under design-basis 
conditions and, if possible, to identify the causes of any failures.  The 
design, testing, and maintenance of all valves and assuring of their 
operability are the responsibility of the licensees.

INEL has concluded that diagnostic systems that measure both stem thrust and 
motor torque are best suited for predicting valve motor performance under 
design-basis conditions.  However, on the basis of INEL's preliminary 
conclusions, it is not clear that tests of an MOV at low or moderate pressure 
differentials can be directly extrapolated to determine correct switch 
settings at design-basis conditions using any type of diagnostic techniques, 
even for single-phase liquid flow.  Currently, the most accurate method of 
determining switch settings and overall competence of the MOV is to perform 
testing at or near design-basis conditions, either in situ or on prototype 
valves. 


However, demonstrating operability in situ at design-basis conditions is not 
practical for some MOVs.  Alternatives to testing at design-basis conditions 
that industry has used include testing at low differential pressure and/or low 
flow, as appropriate, combined with MOV surveillance using suitable signature 
analysis diagnostic techniques.  Licensees should ensure that any tests 
conducted using diagnostic techniques, along with in situ tests conducted at 
conditions less severe than design-basis conditions, will be applied appro-
priately to ensure design-basis operability of safety-related MOVs. 


           

(3)  On February 1, 1989, in Rockville, Maryland, results of the INEL tests 
were described in an NRC sponsored public meeting to review valve blowdown 
tests.  A transcript of the meeting is available from Heritage Reporting 
Corporation, 1220 L Street, N.W., Suite 600, Washington, D.C.  20005.

.                                       3                  June 28, 1989

Licensees should also be aware that increasing MOV thrust by increasing torque 
switch settings, in order to satisfy design-basis operability considerations, 
may subject the valve components to increased forces when the valve is 
operated at no-load or low-load conditions.  Such conditions should be 
evaluated by the licensee to ensure that MOV operability is not compromised.  
The NRC will provide additional information on MOV performance under 
full-scale blowdown test conditions as it becomes available.  Licensees are 
specifically cautioned, however, that the INEL tests are not directed toward 
determining the capability and limitations of various MOV diagnostic systems.  
Therefore, licensees are also encouraged to consider the need for 
industry-sponsored MOV test programs to ensure that diagnostic techniques can 
be used to determine the correct adjustments to ensure operability of those 
safety-related MOVs for which testing at design-basis conditions cannot 
practically be performed in situ. 

Assurance of MOV operability is a complex task.  It involves many factors such 
as development of strong testing and maintenance programs, management support, 
and coordination of engineering, maintenance, and testing.  This effort should 
be viewed by all concerned as a long-term ongoing program.  Licensees that 
have already implemented extensive programs on MOVs have found it very 
beneficial and cost-effective to require that all maintenance and adjustments 
on the MOVs be performed by technicians who have received specific training.  

Surveillance, adjustment, maintenance, and repair of safety-related MOVs 
should be performed in accordance with quality assurance program methods that 
meet the requirements of 10 CFR Part 50.  The recommended actions given in the 
following section are intended to be consistent with NRC's maintenance policy 
statement as published in the Federal Register on March 23, 1988 (53 FR 9430).  
The nuclear power industry has undertaken several generic activities in the 
area of MOV maintenance and testing.  For example, the Electric Power Research 
Institute has published a maintenance guide and intends to publish an 
applications guide for MOVs.  The results of these efforts may be useful to 
the industry in developing an effective program. 

This letter is part of the resolution of Generic Issue II.E.6.1, "In Situ 
Testing of Valves," that relates to MOV testing.

RECOMMENDED ACTIONS 

By this letter NRC extends the scope of the program outlined in Bulletin 85-03 
and Supplement 1 of Bulletin 85-03 to include all safety-related MOVs as well 
as all position-changeable MOVs as defined below.  The licensee's program 
should provide for the testing, inspection, and maintenance of MOVs so as to 
provide the necessary assurance that they will function when subjected to the 
design-basis conditions that are to be considered during both normal operation 
and abnormal events within the design basis of the plant.  Although this 
program should address safety-related MOVs and position-changeable MOVs as a 
minimum, NRC envisions that, as part of a good maintenance program, other MOVs 
in the balance of plant should be considered for inclusion in the program, 
commensurate with the licensee's assessment of their importance to safety. 

Any MOV in a safety-related system that is not blocked from inadvertent 
operation from either the control room, the motor control center, or the valve 
itself should be considered capable of being mispositioned (referred to as 
.                                       4                  June 28, 1989

position-changeable MOVs) and should be included in the program.  When 
determining the maximum differential pressure or flow for position-changeable 
MOVs, the fact that the MOV must be able to recover from mispositioning should 
be considered.

The program to respond to this letter should address items a. through h. 
below.  Items a., b., and c. and the first paragraph of d. are repeated, with 
limited changes, from Bulletin 85-03 or from Supplement 1 of that bulletin.  
The second paragraph of item d. and items e., f., g., and h. provide 
additional clarification and guidance. 

a.   Review and document the design basis for the operation of each MOV.  This 
     documentation should include the maximum differential pressure expected 
     during both the opening and closing of the MOV for both normal operations 
     and abnormal events, to the extent that these MOV operations and events 
     are included in the existing approved design basis.  
     
b.   Using the results from item a., establish the correct switch settings.  
     This should include establishing a program to review and revise, as 
     necessary, the methods for selecting and setting all switches (i.e., 
     torque, torque bypass, position limit, overload) for each valve operation 
     (opening and closing).  One purpose of this letter is to ensure that a 
     program exists for selecting and setting valve operator switches to 
     ensure high reliability of safety-related MOVs.  

c.   Individual MOV switch settings should be changed, as appropriate, to 
     those established in response to item b.  Whether the switch settings are 
     changed or not, the MOV should be demonstrated to be operable by testing 
     it at the design-basis differential pressure and/or flow determined in 
     response to item a.  Testing MOVs at design-basis conditions is not 
     recommended where such testing is precluded by the existing plant con-
     figuration.  An explanation should be documented for any cases where 
     testing with the design-basis differential pressure or flow cannot 
     practicably be performed.  This explanation should include a description 
     of the alternatives to design-basis differential pressure testing or flow 
     testing that will be used to verify the correct settings.  
     
     Note:  This letter is not intended to establish a recommendation for 
     valve testing for the condition simulating a break in the line containing 
     the MOV.  However, a break in the line should be considered in the 
     analyses described in items a., b., and c. if MOV operation is relied on 
     in the design basis.  
     
     Each MOV should be stroke tested, to verify that the MOV is operable at 
     no-pressure or no-flow conditions even if testing with differential 
     pressure or flow cannot be performed.  

d.   Prepare or revise procedures to ensure that correct switch settings are 
     determined and maintained throughout the life of the plant.  These 
     procedures should include provisions to monitor MOV performance to ensure 
     the switch settings are correct.  This is particularly important if the 
     torque or torque bypass switch setting has been significantly raised 
     above that required.  

.                                       5                  June 28, 1989

     It may become necessary to adjust MOV switch settings because of the 
     effects of wear or aging.  Therefore, it is insufficient to merely verify 
     that the switch settings are unchanged from previously established 
     values.  The switch settings should be verified in accordance with the 
     program schedule (see item j.).  The ASME Code Section XI stroke-timing 
     test required by 10 CFR Part 50 is not oriented toward verification of 
     switch settings.  Therefore, additional measures should be taken to 
     adequately verify that the switch settings ensure MOV operability.  The 
     switch settings need not be verified each time the ASME Code 
     stroke-timing test is performed. 

e.   Regarding item a., no change to the existing plant design basis is 
     intended and none should be inferred.  The design-basis review should not 
     be restricted to a determination of estimated maximum design-basis 
     differential pressure, but should include an examination of the pertinent 
     design and installation criteria that were used in choosing the 
     particular MOV.  For example, the review should include the effects on 
     MOV performance of design-basis degraded voltage, including the 
     capability of the MOV's power supply and cables to provide the high 
     initial current needed for the operation of the MOV.  

f.   Documentation of explanations and the description of actual test methods 
     used for accomplishing item c. should be retained as part of the required 
     records for the MOV. 
     
     It is also recognized that it may be impracticable to perform in situ MOV 
     testing at design-basis degraded voltage conditions.  However, the switch 
     settings established in response to item b. should at least be 
     established to account for the situation where the valves may be called 
     on to operate at design-basis differential pressure, or flow, and under 
     degraded voltage conditions.  If the licensee failed to consider degraded 
     voltage, power supply, or cable adequacy for MOVs in systems covered by 
     Bulletin 85-03, the design review and established switch settings for 
     those MOVs should be reevaluated. 
     
     Alternatives to testing a particular MOV in situ at design-basis pressure 
     or flow, where such testing cannot practicably be performed, could 
     include a comparison with appropriate design-basis test results on other 
     MOVs, either in situ or prototype.  If such test information is not 
     available, analytical methods and extrapolations to design-basis 
     conditions, based on the best data available, may be used until test data 
     at design-basis conditions become available to verify operability of the 
     MOV.  If this two-stage approach is followed, it should be accomplished 
     within the schedule outlined in item i. and would allow for MOV testing 
     and surveillance to proceed without excessive delay.

     Testing of MOVs at design-basis conditions need not be repeated unless 
     the MOV is replaced, modified, or overhauled to the extent that the 
     licensee considers that the existing test results are not representative 
     of the MOV in its modified configuration.

g.   A number of deficiencies, misadjustments, and degraded conditions were 
     discovered by licensees, either as a result of their efforts to comply 
     with Bulletin 85-03 or from other experiences.  A list of these 
     conditions 
     .                                       6                  June 28, 1989

     (including improper switch settings) is included in Attachment A to this 
     letter for licensee review and information.  

h.   Each MOV failure and corrective action taken, including repair, 
     alteration, analysis, test, and surveillance, should be analyzed or 
     justified and documented.  The documentation should include the results 
     and history of each as-found deteriorated condition, malfunction, test, 
     inspection, analysis, repair, or alteration.  All documentation should be 
     retained and reported in accordance with plant requirements.

     It is suggested that these MOV data be periodically examined (at least 
     every 2 years or after each refueling outage after program 
     implementation) as part of a monitoring and feedback effort to establish 
     trends of MOV operability.  These trends could provide the basis for a 
     licensee revision of the testing frequency established to periodically 
     verify the adequacy of MOV switch settings (see items d. and j.).  For 
     this monitoring and feedback effort, a well-structured and 
     component-oriented system (e.g., the Nuclear Plant Reliability Data 
     System [NPRDS]) is needed to capture, track, and share the equipment 
     history data.  The NRC encourages the use of the industry-wide NPRDS, 
     appropriately modified, for this purpose in view of the multiple uses for 
     these data.  

SCHEDULE 

The program to respond to this letter should be implemented in accordance with 
the schedule outlined in items i. through k. below.  The scheduled dates 
should ensure that item c. is implemented soonest for those MOVs that the 
licensee considers to have the greatest impact on plant safety.  

i.   Each licensee with an operating license (OL) should complete all design-
     basis reviews, analyses, verifications, tests, and inspections that have 
     been instituted in order to comply with items a. through h. within 5 
     years or three refueling outages of the date of this letter, whichever is 
     later.  Each licensee with a construction permit (CP) should complete 
     these actions within 5 years of the date of this letter or before the OL 
     is issued, whichever is later. 

     For plants with an OL, the documentation described in items 1. and 2. 
     below should be available within 1 year or one refueling outage of the 
     date of this letter, whichever is later.  For plants with a CP, the 
     documentation outlined in items 1. and 2. should be available within one 
     year of the date of this letter or before the OL is issued, whichever is 
     later.  The documents should include: 
     
     1.   The description and schedule for the design-basis review recommended 
          in item a. (including guidance from item e.) for all safety-related 
          MOVs and position-changeable MOVs as described, and 

     2.   The program description and schedule for items b. through h. for all 
          safety-related MOVs and position-changeable MOVs.

j.   The program for the verification of the procedures outlined in item d., 
     as well as other tests or surveillance that the owner may choose to use 
     to identify potential MOV degradations or misadjustments, such as those 
     described 
     .                                       7                  June 28, 1989

     in Attachment A, should be implemented after maintenance or adjustment 
     (including packing adjustment) of each MOV, and periodically thereafter.  
     The surveillance interval should be based on the licensee's evaluation of 
     the safety importance of each MOV as well as its maintenance and perform-
     ance history.  The surveillance interval should not exceed 5 years or 
     three refueling outages, whichever is longer, unless a longer interval 
     can be justified (see item h.) for any particular MOV.  

k.   In recognition of the necessity for preplanning, refueling outages that 
     start within 6 months of the date of this letter need not be counted in 
     establishing the schedule to meet the time limits recommended in items i. 
     and j. 
     
REPORTING REQUIREMENTS

Pursuant to 10 CFR 50.54(f), licensees are required to provide information to 
NRC as outlined in items l. and m. below:

l.   Each licensee shall advise the NRC in writing, within 6 months of the 
     date of this letter, that the above schedule and recommendations will be 
     met.  For any date that cannot be met, the licensee shall advise the NRC 
     of a revised schedule and provide a technical justification in writing.  
     For any recommendation that it cannot meet or proposes not to meet, the 
     licensee shall inform the NRC and provide a technical justification, 
     including any proposed alternative action, in writing. 
     
     Each licensee shall also submit, in writing, any future changes to 
     scheduled commitments; for example, changes made on the basis of trending 
     results (see items h. and j.).  These revised schedules or alternative 
     actions may be implemented without NRC approval.  Justification for the 
     revised schedules and alternative actions should be retained on site. 

m.   Each licensee shall notify the NRC in writing within 30 days after the 
     actions described in the first paragraph of item i. have been completed.

This generic letter supersedes the recommendations in Bulletin 85-03 and its 
supplement.  Bulletin 85-03 addressees need not make any further responses 
regarding that bulletin or its supplement.  The information that was or would 
have been submitted to the NRC in response to Bulletin 85-03 or its supplement 
should be retained in accordance with the recommendations of this generic 
letter. 

Documented results of tests or other surveillances that were used to satisfy 
the recommended actions of Bulletin 85-03 or the supplement to that bulletin 
or a voluntary extension of the recommendations in those documents to other 
MOVs may be used, to the extent applicable, to satisfy the recommendations 
stated herein.  

This request is covered by Office of Management and Budget Clearance Number 
3150-0011, which expires December 31, 1989.  The estimated average burden 
hours are 2000 person-hours per licensee response, including assessing the new 
recommendations, searching data sources, gathering and analyzing the data, and 
preparing the required letters.  These estimated average burden hours pertain 
.                                       8                  June 28, 1989

only to the identified response-related matters and do not include the time 
for the actual implementation of the requested actions.  Comments on the 
accuracy of this estimate and suggestions to reduce the burden may be directed 
to the Office of Management and Budget, Paperwork Reduction Project 
(3150-0011), Washington D.C.  20503, and the U.S. Nuclear Regulatory 
Commission, Records and Reports Management Branch, Office of Information 
Resources Management, Washington, D.C.  20555.

If you have any questions regarding this matter, please contact the NRC Lead 
Project Manager Thierry Ross at (301) 492-3016 or the technical contact listed 
below.



                                       James G. Partlow
                                       Associate Director for Projects
                                       Office of Nuclear Reactor Regulation


Enclosure: Listing of Recently Issued Generic Letters

Technical Contact:
T. Marsh, NRR/EMEB
(301) 492-0902
.                        Attachment A of Generic Letter 
             Summary of Common Motor-Operated Valve Deficiencies,
                    Misadjustments, and Degraded Conditions

1.   Incorrect torque switch bypass settings
2.   Incorrect torque switch settings
3.   Unbalanced torque switch
4.   Spring pack gap or incorrect spring pack preload
5.   Incorrect stem packing tightness
6.   Excessive inertia
7.   Loose or tight stem-nut locknut
8.   Incorrect limit switch settings
9.   Stem wear
10.  Bent or broken stem
11.  Worn or broken gears
12.  Grease problems (hardening, migration into spring pack, lack of grease, 
     excessive grease, contamination, non-specified grease) 
13.  Motor insulation or rotor degradation
14.  Incorrect wire size or degraded wiring
15.  Disk/seat binding (includes thermal binding)
16.  Water in internal parts or deterioration therefrom
17.  Motor undersized (for degraded voltage conditions or other conditions)
18.  Incorrect valve position indication
19.  Misadjustment or failure of handwheel declutch mechanism
20.  Relay problems (incorrect relays, dirt in relays, deteriorated relays, 
     miswired relays) 
21.  Incorrect thermal overload switch settings
22.  Worn or broken bearings.  
23.  Broken or cracked limit switch and torque switch components
24.  Missing or modified torque switch limiter plate
25.  Improperly sized actuators
26.  Hydraulic lockup
27.  Incorrect metallic materials for gears, keys, bolts, shafts, etc. 
28.  Degraded voltage (within design basis)
29.  Defective motor control logic
30.  Excessive seating or backseating force application
31.  Incorrect reassembly or adjustment after maintenance and/or testing
32.  Unauthorized modifications or adjustments
33.  Torque switch or limit switch binding.
Page Last Reviewed/Updated Friday, June 28, 2013