Part 21 Report - 1996-522
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.
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