NUREG-0737 Technical Specifications (Generic Letter No.83-02)
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D. C. 20555
January 10, 1983
TO ALL BOILING WATER REACTOR LICENSEES
Gentlemen:
Subject: NUREG-0737 Technical Specifications (Generic Letter No.83-02)
NUREG-0737, "Clarification of TMI Action Plan Requirements," identifies
those items for which Technical Specifications are required. Technical
Specifications are required to provide assurance that facility operation is
maintained within the limits determined acceptable following implementation
at each facility. The scope and type of specification should include
appropriate actions if limiting conditions for operation cannot be met.
Relevant surveillance requirements for installed equipment should also be
included.
A number of NUREG-0737 items which require Technical Specifications were
scheduled for implementation by December 31, 1981. Each of those items is
present in Enclosure 1. Included in the enclosure is guidance on the scope
of a specification which the staff would find acceptable. Enclosure 2 are
samples in Standard Technical Specification format with blanks or
parentheses appearing where the information is plant specific. It includes
appropriate pages as background information for facilities that do not have
Standard Technical Specifications. These samples are for your information
only.
We solicited comments on proposed Technical Specifications from the boiling
water reactor owners group and Atomic Industrial Forum. Appropriate comments
have been incorporated. We request that you review your facility's Technical
Specifications to determine if they are consistent with the guidance
provided in Enclosure 1. For those items where you identify deviations or
absence of a specification, we request that you submit an application for a
license amendment. The Bases Section should be revised, as appropriate, to
reflect the changes made in Technical Specifications. If some of the items
are not yet implemented at your facility, you should submit an amendment
request at the time they are implemented. Please respond within 90 days of
receipt of this letter.
This request for information was approved by the Office of Management and
Budget under clearance number 3150-0065 which expires May 31, 1983
Sincerely,
Darrell G. Eisenhut, Director
Division of Licensing
Office of Nuclear Reactor Regulation
Enclosures:
As stated
cc: See next page
8301110134
ENCLOSURE 1
STAFF GUIDANCE OF NUREG-0737 TECHNICAL SPECIFICATIONS
(ITEMS SCHEDULED TO BE IMPLEMENTED BY DECEMBER 31, 1981)
(1) STA Training (I.A.1.1.3)
Our July 2, 1980, letter provided model Technical Specifications (TSs)
for TMI lessons learned Category "A" items. Included were TSs that
specified the qualifications, training and on-duty requirements for the
Shift Technical Advisors (STA). STA training requirements are under
consideration by the Commission. Further guidance will be provided
pending decision regarding engineering expertise on shift by the
Commission.
(2) Limit Overtime (I.A.1.3)
On June 15, 1982 we transmitted to licensees a revised version of the
Commission's Policy Statement on nuclear power plant staff working
hours. In the same letter we also transmitted revised pages to
NUREG-0737 (Item 1.A.1.3). The administrative section of the technical
specifications should be revised to require procedures that follow the
policy statement guidelines. An acceptable specification would, be "the
amount of overtime worked by plant staff members performing
safety-related functions must be limited in accordance with the NRC
Policy Statement on working hours (Generic Letter No. 82-12)," or
following the model TSs in Enclosure 2.
(3) Dedicated Hydrogen Penetrations (II.E.4.1)
Plants that use external recombiners or purge/repressurization systems
for post-accident combustible gas control of the containment atmosphere
should provide containment penetrations dedicated to that service. The
acceptable alternative is a combined design for use by either external
recombiners or purge/repressurization systems and other systems which
meet the requirements of Section 50.44 of 10 CFR Part 50. In satisfying
this item, some plants may have to add some additional piping and
valves. If so, these valves should be subjected to the requirements of
Appendix J, and the TSs should be modified accordingly.
(4) Containment Pressure Setpoint (II.E.4.2.5)
The containment pressure setpoint that initiates containment isolation
must be reduced to the minimum compatible with normal operating
conditions. Most plants provided justification for not changing their
setpoint and we approved their justifications by separate
correspondence. The remaining plants have submitted a change to the TSs
with the lower containment pressure setpoint. No further actions are
required.
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(5) Containment Purge Valves (II.E.4.2.6)
Model TSs are being sent separately to each plant as part of the
overall containment purge and vent system review, Technical
Specifications will be reviewed separately for each plant. In general,
these TSs include the requirement that:
a. Containment purge or vent valves be locked closed if found not f
qualified for operation during a LOCA, and be verified locked
closed at least every 31 days;
b. Containment purge or vent valves be used only when needed for
safety related reasons;
c. Containment purge or vent valves with resilient seals be sub-
jected to leakage testing and periodic resilient seal replacement.
Allowable time period in each year for purge/vent operation at each
plant will be considered on a case-by-case basis.
(6) Radiation Signal on Purge Valves (II.E.4.2.7)
NUREG-0737 requires that containment purge and vent isolation valves
must close on a high radiation signal to reduce the amount of radiation
released outside containment following a release of radioactive
materials to containment. The BWR Owners' Group has taken exception to
this requirement and submitted their evaluation to NRC. NRC is
currently reviewing the latest submittal of the Owners' Group.
Technical Specifications for this item will be established after the
technical resolution of this issue is completed.
(7) Reporting SV and RV Failures and Challenges (II.K.3.3)
NUREG-0660 stated that safety and relief valve failures be reported
promptly and challenges be reported annually. The sections of your TSs
that discuss reporting requirements should be accordingly changed;
model TSs are given in Enclosure 2. Note that an acceptable alternative
would be to report challenges monthly.
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(8) RCIC Restart and RCIC Suction (II.K.3.13, II.K.3.22)
The design of RCIC should be modified such that:
1) The system will restart on subsequent low water level after it has
been terminated by a high water level signal;
2) RCIC system suction will automatically switchover from the
condensate storage tank to the suppression pool when the
condensate storage tank level is low.
Provide technical specifications for both of the above modifications.It
could be included with other technical specifications for the RCIC
system. Typical acceptable limiting conditions for operation (LCO) and
surveillance requirements, for instrumentation and system operational
capability, are given in Enclosure 2.
(9) Isolation of HPCI and RCIC Modification (III.K.3.15)
The pipe break-detection circuitry should be modified so that pressure
spikes resulting from HPCI and RCIC system initiation will not cause
inadvertent system isolation. The plants using a time delay relay for
this modification should change their technical specification to
include the time delay added by the relay in the isolation system
instrumentation response time. The minimum and maximum expected
response time should be provided as discussed in the sample TSs (in
Enclosure 2).
The minimum expected response time is a plant specific value. The
maximum expected response time should not be higher than seven seconds
unless the licensee provides proper justification for selecting a
higher response time. The plants which don't have isolation system
response time in their Technical Specifications, should include the
setpoint and the surveillance requirements on the time delay relay in
the TSs.
(10) Interlock on Recirculation Pump Loops (II.K.3.19)
Interlocks are required on nonjet pump plants (other than Humboldt Bay)
to assure that at least two recirculation loops are open for
recirculation flow for modes other than cold shutdown. This is to
assure that the level measurements in the downcomer region are
representative of the level in the core region.
Since there are very few plants affected by this modification and the
change may be plant specific, we advise these plants to develop the
technical specification and submit to the staff. The technical
specification should include some surveillance requirements on the
instrumentations and the corrective actions to be taken in case of
instrumentation malfunction or failure.
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(11) Common Reference Level (II.K.3.27)
All level instruments should be referenced to the same point. If a
figure defining reactor vessel water levels is included in the
Technical Specifications of your plant, it should be changed to reflect
the common reference level established by this Action Plan Item. A
sample figure is given in Enclosure 2.
(12) Manual Depressurization (II.K.3.45)
Technical resolution of this Action Plan Item has just been completed.
The staff will not require any modifications in plant design and
operation. Therefore no changes to Technical Specifications will be
required.
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