ML18019A560
| ML18019A560 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 01/27/1986 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NLS-85-463, NUDOCS 8602030242 | |
| Download: ML18019A560 (8) | |
Text
REGULATOR FORMATION DI.STR I BUT I ON S EM
( R IDS )
ACCESSION NBR: 8602030242 DOC. DATE: 86/Oi/27 NOTARIZED:
NO DOCKET ¹ FACIL: 50-400 Shearon Harris Nuclear Power Planti Unit ii Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION CUTTERi A. B.
Carolina Power
& Light Co.
RECIP. NAME RECIPIENT AFFILIATION DENTONi H. R.
Office of Nuclear Reactor'egulationi Director (pre-851125)
SUBJECT:
Forwards responses to Pump
& Valve Operability Review Team
& SGRT during 851202-06 audit of seismic
& pump
& valve operability review programs. Remaining open comments will be addressed shortly.
DISTRIBUTION CODE:
B001D COPIES RECEIVED: LTR ENCL SIZE:
TITLE: Licensing Submittal:
PSAR/FSAR Amdts
& Related Correspondence NOTES:
RECIPIENT ID CODE/NAME PWR-A ADTS PWR-A EB PWR-A FOB BUCKLEYiB 01 PWR-* RSB INTERNAL: ACRS 41 ELD/HDS1 IE/DEPER/EPB 36 NRR BWR ADTS NRR PWR-B ADTS NRR/DHFT/HFIB N
RO DIR R 9 FIL 04 NFD I/MIB EXTERNAL: 24X DMB/DSS (AMDTS)
NRC PDR 02 PNL QRUELz R COPIES LTTR ENCL 1
1 1
1 1
2 2
1 1
6 6
1 0
1 1
1 0
1 0
1 1
1 0
1 1
1 0
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PWR-A PD2 PD PWR-A EICSB PWR-A PD2 LA PWR-A PSB ADM/LFMB IE FILE IE/DGAVT/GAB 21 NRR PWR-A ADTS NRR ROE> M. L NRR/DHFT/MTB NRR/DSRO/RRAB RQN2 BNL(AMDTS ONLY)
LPDR 03
'NSI C 05 COPIES LTTR ENCL 1
1 1
1 1
1 1
1 0
1 1
1 1
1 0
1 1
1 1
1 1
3 3
TOTAL NUMBER OF COPIES REGUIRED:
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ÃQE Carolina Power & Light Company JAN 2 '7 1986 SERIAL: NLS-85-063 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. l DOCKET NO.50-000 SEISMIC QUALIFICATIONAND PUMP AND VALVEOPERABILITY REVIEWS
Dear Mr. Denton:
On December 2-6, your Staff conducted an audit of the Shearon Harris Seismic Review Program and the Pump and Valve Operability Review Program.
Enclosures l and 2
provide answers to comments made by the Pump and Valve Operability Review Team and the Seismic Qualification Review Team, respectively.
We are working to address the remaining open comments as expeditiously as possible.
ff you have any questions with regard to this issue, please contact Mr. Pedro Salas at (9l9) 836-80l5.
Yours very truly, ABC/PS/ljs (3172PSA)
Enclosure A.. Cut r - Vice Presid nt Nu ngineering k Licensing Cct Mr. G. Bagchi (NRC)
Mr. B. C. Buckley (NRC)
Mr. 3. Lombardo (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. 3. Nelson Grace (NRC-RII)
Mr. C. Kido (EGRG)
Mr. 3. Singh (EG&G)
Mr. Travis Payne (KUDZU)
Mr. Daniel F. Read (CHANGE/ELP)
Wake County Public Library Mr. Wells Eddleman Mr. 3ohn D. Runkle Dr. Richard D. Wilson Mr. G. O. Bright (ASLB)
Dr. 3. H. Carpenter (ASLB)
Mr. 3. L. Kelley (ASLB)
Mr. H. A. Cole PDR gD~<> 860227 f; 2030 OCR 05000000
~
PDRL
'11 Fayettevilte Street
~ P. O. Box 1551 o Raleigh, N. C. 27602
j~
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a
ENCLOSURE 1
PUMP R VALVEOPERABILITYREVIEW TEAM COMMENTS Comment 1:
Valve 35W-BISA-1:
Verify what equipment could be affected if water accumulates in area where valve is located.
Answer:
Only a single pipe containing the valve of interest and its appurtenances are in the area where the valve is located.
The only major source of water would be a failure in this piping line.
This area is inspected by Operations personnel during daily operator walkdowns. If problems exist in this area, appropriate measures will be taken at that time.
CPRL considers this item closed.
Comment 2:
Answer:
Valve 3AF-F3SA-1 has not been tested to prove it can open against design delta pressure.
As stated during the audit, SHNPP agreed to perform a pre-operational test to verify that the valve will perform as required.
SHNPP has performed this test in conjunction with the startup process and has verified that the valve will perform its function with adequate margin.
CPRL considers this item closed.
Comment 3:
Answer:
Emergency service water pump P1A-SA:
During post-construction operation, a bearing failure occurred.
This was reported to the NRC through the normal reportability system.
The PORV team requested a
copy of the final report when it is issued by CPRL.
As stated during the audit, an interim report was issued documenting the failure, cause and preventive measures taken to date by CPRL.
A copy of this report was given to the team.
A final report is scheduled to be released by CPRL on March 1, 1986.
Comment 0:
Answer:
Valve 3CC-V165-SA has been analyzed by Westinghouse for operability.
The NRC requires either data from a test or a similarity analysis to a test of a like valve as backup to the analysis.
'his valve is on the active valve list because following a LOCA the decay heat is removed from the primary via the RHR heat exchanger and the component cooling water system.
Therefore, this valve needs to be operated approximately 20 minutes following a large LOCA to continue decay heat removal from the containment.
During the postulated event (LOCA and SSE), it is closed and receives no LOCA loads, only the SSE loads.
In this condition (with the valve disc firmly on its seat), it is very reasonable to assume the valve internals remain functional.
The valve operator is a 'qualified Limitorque for which we have actual test reports.
Considering the normal position of the valve, the fact it does not move during an event (called upon well after a LOCA in conjunction (3172PSA/I js )
with a SSE), the in-depth analysis work that has been performed, the actual test data of the valve operator and the functional activity class of the component, CPRL believes the valve has been demonstrated to be functional and remain functional following a Design Basis Event (DBE) complete with an SSE.
GENERAL COMMENT
S Comment 5:
The NRC requires confirmation that the FSAR active valve list has been reviewed and is correct prior to fuel load.
Answer:
The FSAR active valve list was undergoing review prior to the team visit. A copy of the proposed revision was given to the team.
CPRL will revise the FSAR table when these reviews are complete.
Comment 6:
The NRC requires that all pre-service testing be complete prior to operation.
Answer:
It is CPRL's intent to complete pre-service testing prior to operation.
Comment 7:
The NRC requires confirmation that all safety related active pumps and valves are qualified prior to fuel load.
Answer:
CPRL will confirm qualification of safety related active pumps and valves to the NRC prior to fuel load.
(3172PSA/I js)
ENCLOSURE 2 SEISMIC UALIFICATIONREVIEW TEAM COMMENTS Comment 1:
Valve 2SI-V570-SBl needs stress analysis that correlates test data provided in qualification report.
Answer:
CPRL and Westinghouse are currently working on this item.
Requested data willbe provided by February 1, 1986.
Comment 2:
Solid state protection system test cubicle cabinets hinge pins on the doors are falling out and the doors are. not secure.
Answer:
Subject hinges and doors were repaired prior to audit exit.
A walk through survey was conducted to ascertain that the item was an isolated occurrence.
CPdcL considers this item closed.
Comment 3:
Radiation monitor cabinet seismic report reviewed by the NRC was only for cabinet.
NRC requested verification that the internal components are qualified.
Answer:
The internal components are qualified.
CPRL and Ebasco are reviewing the final qualification reports at this time.
Final approval is anticipated by March 15, 1986.
Comment 0:
Emergency service water pump.
Additional information was requested concerning building movements of the emergency service water intake structure.
Answer:
All requested information was provided to the NRC team prior to their exit from the site.
CPRL considers this item closed.
(3172PSA/I js )