ML20195E615
| ML20195E615 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 06/02/1986 |
| From: | Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | William Cahill GULF STATES UTILITIES CO. |
| References | |
| IEB-85-003, IEB-85-3, NUDOCS 8606090169 | |
| Download: ML20195E615 (1) | |
Text
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o MI E Docket: 50-458
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Gulf States Utilities ATTN: William J. Cahill, Jr.
Senior Vice President River Bend Nuclear Group P. O. Box 2951 Beaumont, Texas 77704 Gentlemen:
Thank you for your letter of May 14, 1986, in response to NRC IE i
Bulletin (IEB)85-03.
In your letter, you requested an extension to finalize.
your response to IEB 85-03, item (e), in order to utilize the efforts of the BWR Owners' Group (BWR0G). Your request for an extension is granted until 30 days following the development of a generic BWR position by the BWROG.
1 Sincerely, Original Signed By J. E. Gagliardo J. E. Gagliardo, Chief Reactor Projects Branch cc:
Gulf States Utilities ATTN:
J. E. Booker, Manager-Engineering, Nuclear Fuels & Licensing j
P. O. Box 2951 l
Beaumont, Texas 77704 Louisiana State University, Government Documents Department Louisiana Radiation Control Program Director bectoDMB(IE01) 8606090169 e60602 PDR ADOCK 05000458 bec distrib. by RIV:
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Resident Inspector R. D. Martin, RA SectionChief(RPB/A)
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GULF STATES UTILITIES COMPANY POST OF5 BCE BOk 2951.
BEAUMONT T E*AS 77704 AREA CODE 409 eJ8 6631 May 14, 1986 RBG-23,678 File No(s). G9.5, G9.33.1 Mr. Robert D. Martin, Regional Administrator U. S. Nuclear Regulatory Commission Q
Region IV l
611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 ggg l.
Dear Mr. Martin:
__ L River Bend Station - Unit 1 Docket No. 50-458 NRC I&E Bulletin 85-03 This letter provides Gulf States Utilities Company's (GSU) 180 day response to NRC I6E Bulletin 85-03 (IEB 85-03) " Motor-operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings". The BWR Owners' Group (BWROG), of which GSU is a member, has undertaken the task of developing a generic BWR position for meeting the requirements of IEB 85-03 as indicated in their letter dated April 29, 1986 (Reference BWROG-8619, from J. M. Fulton-Chairman BWROG to J. M.
Talyor, NRC). The BWROG position is scheduled to be completed in September 1986. Because of the generic implications, GSU requests an extension to finalize its response to IEB 85-03 (item e) in order to utilize the BWROG efforts.
Attached please find GSU's preliminary response to IEB 85-03.
GSU anticipates the final results of item (a) will be provided within 30 days of the completion of the BWROG position. The program to complete items (b) through (d) is scheduled to be completed by November 15, 1987 as required by the Bulletin. The report required by item (f) will be provided within 60 days of completion of the program.
Should you have any questions feel free to contact us.
Sincerely,
?hc 4 J. E. Booker Manager-Engineering, Nuclear Fuels & Licensing River Bend Project
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2 ATTACHMENT TO RBG-23,678 Item (a)
GSU plans to utilize the efforts of the BWROG to assist in the determination of the maximum differential pressure expected across each identified motor-operated valve (MOV) as required by item (a). Although the BWROG position is not scheduled to be completed by September 1986, GSU has completed a preliminary review of the High Pressure Core Spray (HPCS) System and the Reactor Core Isolation Cooling (RCIC) System to identify the MOVs and maximum differential pressures expected that are within the scope of IEB 85-03.
The following is a preliminary list of each MOV and maximum differential pressure expected identified as a result of this review:
(1)
(2)
(3)
(4)
(5)
Maximum Differential System Valve Tag Size (in)
Tyge Pressure Expected HPCS E22*F001 16 GATE 14 HPCS E22*F004 10 GATE 1400 HPCS E22*F010 10 GLOBE 1427 RPCS E22*F011 10 GLOBE 1427 HPCS E22*F012 4
GATE 1427 HPCS E22*F015 20 GATE 17 HPCS E22*F023 10 GLOBE 1427 RCIC E51*C002 4
GLOBE 1130 RCIC E51*F010 6
GATE 12 RCIC E51*F013 6
GATE 1375 RCIC E51*F019 2
GLOBE 1371 2
RCIC E51*F022 4
GLOBE 1385 3
RCIC E51*F031 6
GATE 17 RCIC E51*F045 4
GLOBE 1130 RCIC E51*F046 2
GLOBE 1385 RCIC E51*F059 4
GATE 1385 RCIC E51*F063 8
CATE 1025 RCIC E51*F064 8
GATE 1025 RCIC E51*F068 12 GATE 25 RCIC E51*F076
.75 GLOBE 1025 RCIC E51*F077 1.5 GLOBE 8
RCIC E51*F078 2.5 GLOBE 8
S RBG-23,678 l
Attachment Page 2 l
l Heading Explanations for Above List l
(1)
System in which a valve is located.
l HPCS - High Pressure Core Spray l
RCIC - Reactor Core Isolation Cooling (2)
Valve Tag is a unique identifying number for each valve. The asterisk (*) in the number indicates a Category I (safety related) valve.
(3)
Size is the valve size in inches as specified in the Design Specification Data Sheet (DSDS) for that Valve Tag No.
(4)
Type is either gate or globe as specified on the DSDS.
(5)
Preliminary maximum differential pressure expected to occur across a valve when the valve is required to operate under worst case conditions analyzed in the RBS FSAR.
o RBG-23,678 Attachment Page 3 Item (b)
Upon completion of the BWROG position and the finalization of the maximum differential pressures expected as required by item (a), GSU will establish the switch setpoints (i.e., torque, torque bypass, position limit and motor overload) and tolerances for each motor i
operated valve identified. Prior to any testing GSU will determine the field settings of the MOV switches in order to confirm correct switch settings.
Item (c)
Any valve with settings that are non-conservative or out of tolerance as defined by item (b) will be reviewed for any impact on system operability and will be reset as necessary in accordance with applicable procedures to the more conservative values.
Settings to be included are limit switch set points, open and closed; torque switch settings, open and closed; and torque switch bypass switch settings, open and closed.
Appropriate test procedures will be developed for any necessary testing.
Based on the current program, CSU plans to begin any necessary testing just prior to the first refueling outage for River Send Station (RBS).
The first refueling outage for RBS is currently scheduled to begin in April 1987.
Item (d)
Appropriate procedures involving the valves identified in response to this Bulletin will be reviewed and revised as necessary to maintain the settings determined in item (b). All procedure reviews will be completed and any changes approved prior to completion of the program.
Item (f)
The final report will be submitted to the NRC within 60 days of completion of the program. Should this schedule change significantly, GSU will advise the NRC.
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION STATE OF TEXAS COUNTY OF JEFFERSON In the Matter of 5
Docket Nos. 50-458 GULF STATES UTILITIES COMPANY (River Bend Station, Unit 1)
AFFIDAVIT J. E. Booker, being duly sworn, states that he is Manager-Engineering Nuclear Fuels, and Licensing; that this position requires him to submir documents to the Nuclear Regulatory Commission in behalf of Gulf States Utilities; that the documents attached hereto are true and correct to the best of his knowledge, information and belief.
t d.F. L b, fJ. E. Booker A
Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this / Y day of
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Notary Public in and fo(
Jefferson County, Texas My Commission Expires:
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