ML17279A930
| ML17279A930 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/29/1988 |
| From: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| References | |
| IEB-85-003, IEB-85-3, NUDOCS 8804040245 | |
| Download: ML17279A930 (5) | |
Text
1 ACCEIZMTED DIFKIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8804040245 DOC.DATE: 88/03/29 NOTARIZED: NO DOCKET g
FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH.NAME AUTHOR AFFILIATION KIRSCH,D.F.
Region 5, Ofc of the Director, RECIP.NAME RECIPIENT AFFILIATION SORENSEN,G.C.
Washington Public Power Supply System
SUBJECT:
Recpxests addi info re util 860528,1001
& 871218 responses to IE Bulletin 85-003.
DISTRIBUTION CODE:
IEOID COPIES RECEIVED:LTR &CLQ SIZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES RECIPIENT ID CODE/NAME PD5 PD INTERNAL: AEOD NRR MORISSEAU,D NRR/DLPQ/QAB10A NRR/DREP/EPBlOD NRR/DRIS DIR9A2 OE B
,J F
02 G
FILE 01 EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1
.RECIPIENT ID CODE/NAME SAMWORTH,R J
DEDRO NRR/DLPQ/PEB11B NRR/DOEA DIR11E NRR/DREP/RPB10A NRR/PMAS/ILRB12 OGC 15-B-18 RES/DRPS DIR NRC PDR COPIES LTTR ENCL 2
2 1
1 1
1 1
1 2
2 1
1 1
1 1
1 A
A TOTAL NUMBER OF COPIES REQUIRED:
LTTR 22 ENCL 22
March 29, 1988
& OR t9R XIQ' 304 63')
WC 4) ave Docket No. 50-397 Washington Public Power Supply System P. 0.
Box 968 3000 George Washington Way
- Richland, Washington 99352 Attention:
Mr. G.
C. Sorensen, Manager WNP-2 Regulatory Programs
Subject:
Request for Additional Information Concerning WNP-2 Response to IEB 85-03 Washington Public Power Supply's letters of May 28, 1986 and October 1, 1986, and December 18, 1987, partaining to WNP-2, contained the responses to IEB 85-03, "Motor Operated Valve Common Mode Failures during Plant Transients Due to Improper Switch Settings".
A review of the responses indicates the need for additional information before the program to assure valve operability can be approved.
The specific information requested is enclosed in the attachment.
The information requested in, the attachment should be sent within 30 days of the date of this letter to:
Richard J. Kiessel Division of Operational Events Assessment Nuclear Regulatory Commission Washington, D.C. 20555 A copy of this response should also be sent to the NRR Project Manager for WNP-2 and to the Regional Office.
Sincerely,
/sg Dennis F. Kirsch, Director Division of Reactor Safety and Projects, RV Encl osure:
1.
RAI for WNP-2 cc w/enclosure (1):
D. Kirsch.
RV J. Melfi, RV R. Kiessel, NRR R. Sammworth, NRR RV/jk EST COPY REQUEST Y
REQUEST=-
VEST COPY ]
/
NO YES /
N YES /
NO YES /
NO
]
D R
S /
NO MELFI 7/ 4 RICHARDS%~
PATE~~'
KIRSCH 3/<0 88
'3/IA'//88 3/jgj /88 3g /88
MAR 18 1988 Page 1 of 3
REQUEST FOR ADDITIONAL INFORMATION (RAI) RE:
Review of Responses to Action Item e of IE Bulletin 85-03 Licensee:
Washington Public Power Supply System P. 0.
Box 968 3000 George Washington Way
- Richland, Washington 99352-0968 Unit(s):
WNP 2
Date of Response:
05-28-86 10-01-86
<<12-18-87
<<This response to Action Item f has not been reviewed completely.
Respondent:
G.
C. Sorensen, Manager Regulatory Programs The information provided in your response to Action Item e of IE Bulletin 85-03 was found to be deficient in some areas.
Provide the additional information necessary to resolve the following comments and questions:
- 1. Revise the table enclosed with the response of 10-01-86 to include values of differential pressure for opening the following MOVs, or justify their exclusion.
Note that assumption of inadvertent equipment operations is required by Action Item a of the bulletin.
(a)
MOV HPCS-V-l is shown normally open in Zone C-7 of Drawing M520 Revision 53, and as MOV 3 on Page 67 of BWROG Report NEDC-31322 dated September 1986.
How would suction from the CST be ensured if this valve were to be (a) actuated inadvertently to the closed position upon intended initiation of the system or (b) left closed inadvertently?
(b)
MOV RCIC-V-10 is shown normally open in Zone B-14 of Drawing M519 Revision 50, and as MOV 3 on Page 72 of the BWROG Report.
The question in Item l(a) above applies here also.
(c) Trip and Thr'ottle MOV RCIC-V-1 is shown normally open in Zone E-ll of Drawing M519 Revision 50, and as MOV X on Page 74 of the BWROG Report.
How would steam supply to the RCIC turbine be ensured if this MOV were to be operated inadvertently as described in Item 1(a) above?
MAR 18 1988 Page 2 of 3 RAI for WNP 2
- 2. Revise the "table enclosed. with the response dated 10-01-86 to include MOVs 'RCXC-V-110 and -113, or )ustify their exclusion.
These. valves 'are. shown in Zone.E-7 of Drawing M519 Revision 50, and as MOVs VII and VIII on Page 74 of the BWROG Report.
These MOVs are listed in responses for the other GE Class 5 plants.
- 3. Revise the table enclosed with the response of 10-01-86 to include values of differential pressure for opening HPCS MOVs V-10, V-11 and V-23.
These valves are shown normally closed as test MOVs 5, 6 and 7 on Page 67 of the BWROG Report.
According to Page 55 of that report, these valves have no safety actions; however, utilities are expected to report differential pressures for testing, per Note o on Page 66 of that report.
- 4. The response of 12-28-87 indicates. that MOVATS has been included in the MOV testing program.
If MOVATS is planned for application to some MOVs which are not included'n its data
- base, commit to and describe. an alternate method for determining the extra thrust necessary to,overcome the pressure differentials for these valves.
5.
The proposed program for action items b, c and d of the bulletin,is.incomplete.
Provide the following details as'a
'mi'nimum (a) 'commitment to a training program for 'setting switches, maintaining valve operators, using the diagnostic/test equipment,and interpreting results of the diagnostic tests, (b) commitment to )ustify continued operation of a valve determined to be inoperable, (c) description of s method possibly needed to extrapolate valve stem thrust determined by testing at less than maximum differential pressure, (d) justification of a possible alternative to testing at maximum differential pressure at the plant, (e) consideration of pipe break conditions as required by the
- bulletin, (f) stroke testing when necessary to meet bulletin requirements, and
MAR IS ]S9Q Page 3 of 3
(g) consideration of applicable industry recommendations in the preparation of procedures to ensure maintenance of correct switch settings.
Note:
A partial review of the response of 12-18-87 indicates that comments 1,
2 and 3 apply to it as well as to the earlier response.