United States Nuclear Regulatory Commission - Protecting People and the Environment

ACCESSION #: 9612020106

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Commonwealth Edison Company
LaSalle Generating Station
2601 North 21st Road
Marseilles, IL 61341-9757
Tel 815-357-6761

                                                  ComEd

November 27, 1996

United States Nuclear Regulatory Commission
Attention: Document Control Desk
Washington, D.C. 20555

Subject:       LaSalle County Station Units 1 and 2
               10 CFR Part 21 Notification 9605 Final Report
               NRC Docket Numbers 50-373 and 50-374

Reference:     Letter from W. T. Subalusky to US Nuclear Regulatory
               Commission, LaSalle County Station Units 1 and 2, 10 CFR
               Part 21 Notification 9605, dated October 4, 1996.

Enclosed is ComEd's 10 CFR Part 21 Notification of the deficiency of WKM
model 70-13 Pneumatic Actuators manufactured by the Anchor Darling Valve
Company and in use at LaSalle County Station.  This notification is
submitted in accordance with the requirements of 10 CFR 21, Section
21.1(b).  An interim notification, referenced above, had been made in
accordance with 10 CFR Part 21 Section 21.21 (a)(2).

If there are any questions or comments concerning this letter, please
refer them to me at (815) 357-6761, extension 3600.

Respectfully,

W. T. Subalusky
Site Vice President
LaSalle County Station

Enclosure

cc:  A. B. Beach, NRC Region III Administrator
     M. P. Huber, NRC Senior Resident Inspector - LaSalle
     D. M. Skay, Project Manager - NRR - LaSalle
     F. Niziolek, Office of Nuclear Facility Safety - IDNS
     DCD - Licensing (Hardcopy:    Electronic:    )
     Central File

                       10CFR Part 21 Notification

                   10 CFR Part 21 Report (File 96-05)
                 WKM, MODEL 70-13 PNEUMATIC ACTUATORS -
                   INCORRECT EFFECTIVE DIAPHRAGM AREA

Applicability       This notification is submitted in accordance with the
                    requirements of 10CFR Part 21, Section 21.1 (b).  An
                    interim notification had been previously made on
                    October 4th, 1996 in accordance with 10CFR Part 21
                    Section 21.21(a)(2).

Identification of Facility and Component     LaSalle County Station,
                                               Units One and Two
                                             Commonwealth Edison
                                             Chicago, Illinois

                                             WKM. Model 70-13 pneumatic
                                             actuators (sizes 35, 70,
                                             140, 280)

Identification of Component Manufacturer     Anchor Darling Valve Company

Nature of Defect

Anchor Darling Valve Company performed effective diaphragm area (EDA)
testing on the various WKM, Model 70-13 pneumatic actuators (sizes 35,
70, 140, 280).  The preliminary test results indicated that the original
effective diaphragm area values used to calculate the bench set and
supply air set points were incorrect.

Safety Significance

Potentially, the listed Primary Containment Isolation System (PCIS) valve
assemblies would not provide adequate system isolation under designed
accident conditions.  The PCIS function may not have operated if
required.

LaSalle Unit One is in Cold Shutdown mode and Unit Two is in Refuel mode.
The PCIS function for the listed valves is not required for these modes.

Updated Safety Significance:

See Licensee Event Report #96-011-00

Time of Discovery

September 28, 1996

Corrective Actions

From the October 4, 1996, notification:

1) All affected valves are being reviewed/evaluated, design changes are
being initiated as required.

It should be noted that the WKM Series 70-13 actuator is currently
manufactured by the Anchor Darling Valve Company and similar valves may
have been previously manufactured under the "Muesco" or "B, S & B"
designations.

2) LaSalle is awaiting the publication of Anchor Darlings final testing
report.  A final notification will be made at that time.

                10 CFR Part 21 Final Report (File 96-05)
                                                                        2

1) Design changes for all affected Primary Containment Isolation System
(PCIS) and Reactor Core Isolation System (RCIC) valves have been
initiated to make the required setting adjustments to ensure adequate
design margins.  Both units will remain in a condition that doesn't
require valve design operation until the problem is corrected.

2) Licensee Event Report #96-011-00
Title: "Pneumatic valves with less-than-designed effective diaphragm area
results in inadequate valve closing forces which may affect containment
isolation."
Submittal Date: October 28, 1996.
Docket #050-373

3) In the interim report it was stated that LaSalle was awaiting the
publication of Anchor Darling's Final Testing Report and would be making
a final notification not that time.  At that time, Anchor Darling's
projected date for completion of the report was the mid-October time
frame.  As the result of recent conversations between Anchor Darling and
ComEd, it is now LaSalle's understanding that the projected completion
date of the final report has been pushed back to an end of November time
frame.  In addition, it is Anchor Darling's stated intention not to
release the final report to LaSalle County Station.

Conclusion

LaSalle County Station's Licensee Event Report #96-011-00, will be
followed by a supplemental report to be issued by December 2, 1996.  The
supplemental report will provide an updated assessment of the safety
consequences of the event and will be based upon an analysis of as-found
testing data of the affected valves.

All questions related to the results of Effective Diaphragm Area (EDA)
testing should be addressed to the Anchor Darling Corporation.

    PCIS Valves appear in Bold Italics and are marked with an asterisk *.

                10 CFR Part 21 Final Report (File 96-05)
                                                                        3

Table "Number and Location of All Defective Components", pages 3, 4, & 5,
omitted.

Contacts

Mark Smith
AOV Component Engineer
LaSalle County Station
Commonwealth Edison
2601 North 21st Road
Marseilles, Illinois 61341
(815) 357-6761

    PCIS Valves appear in Bold Italics and are marked with an asterisk *.

GENERAL INFORMATION or OTHER                 EVENT NUMBER: 31093

LICENSEE: LASALLE COUNTY STATION        NOTIFICATION DATE:  10/04/96
    CITY:                REGION: 3      NOTIFICATION TIME:  15:35 [ET]
  COUNTY:                 STATE: IL     EVENT DATE:         09/28/96
LICENSE#:             AGREEMENT: Y      EVENT TIME:         12:00[CDT]
  DOCKET:                               LAST UPDATE DATE:   11/27/96

                                                  NOTIFICATIONS
NRC NOTIFIED BY: MR. SUBALUSKY
HQ OPS OFFICER:  DOUG WEAVER            VERN HODGE          NRR

EMERGENCY CLASS: NOT APPLICABLE
10 CFR SECTION:
CCCC 21.21     UNSPECIFIED PARAGRAPH

                               EVENT TEXT

PART 21 NOTIFICATION ON WKM MODEL 70-13 PNEUMATIC ACTUATORS

ANCHOR DARLING VALVE COMPANY PERFORMED EFFECTIVE DIAPHRAGM AREA
(EDA)
TESTING ON THE VARIOUS WKM MODEL 70-13 PNEUMATIC ACTUATORS (SIZES 35,
70,
140, 280).  THE PRELIMINARY TEST RESULTS INDICATED THAT THE ORIGINAL
EFFECTIVE DIAPHRAGM AREA VALUES USED TO CALCULATE THE BENCH SET
AND
SUPPLY AIR SET POINTS WERE INCORRECT.  THESE ACTUATORS ARE USED ON
VARIOUS PRIMARY CONTAINMENT ISOLATION VALVES AND THESE VALVES
MAY NOT
PROVIDE ADEQUATE SYSTEM ISOLATION UNDER DESIGN ACCIDENT
CONDITIONS.

LASALLE UNIT ONE IS IN COLD SHUTDOWN AND UNIT TWO IS IN THE REFUEL
MODE.

* * * UPDATE RECEIVED BY FAX AT 1508 ON 11/27/96, TAKEN BY WEAVER * * *

DESIGN CHANGES FOR ALL AFFECTED PRIMARY CONTAINMENT ISOLATION
SYSTEM
(PCIS) AND REACTOR CORE ISOLATION SYSTEM (RCIC) VALVES HAVE BEEN
INITIATED TO MAKE THE REQUIRED SETTING ADJUSTMENTS TO ENSURE
ADEQUATE
DESIGN MARGINS.  BOTH UNITS WILL REMAIN IN A CONDITION THAT DOESN'T
REQUIRE VALVE DESIGN OPERATION UNTIL THE PROBLEM IS CORRECTED.

THE LICENSEE SUBMITTED AN LER ON THIS TOPIC ON 10/28/96.  AN UPDATED LER
WILL BE SUBMITTED ON 12/2/96.  THE HOO NOTIFIED VERN HODGE OF THIS
UPDATE.

FAX                           Date      11/27/96

                              Number of pages including cover sheet  7

TO:  Nuclear Regulatory       FROM:     W. T. Subalusky
     Commission                         LaSalle County Nuclear
     OPS Center                         Power Station

                              Phone     815-357-6761
FAX Phone    301-816-5151     Fax Phone 815-357-6761, ext. 2502
VERIFICATION 301-816-5100

RE:  LaSalle County Station
     Units 1 and 2
     10CFR Part 21
     Notification 9605
     Final Report

REMARKS: X Urgent   For your review     Reply ASAP     Please Comment

Attached are the above-entitled documents including cover letter; and
10CFR Part 21 Notification.

*** END OF DOCUMENT ***

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