ML17164B059
| ML17164B059 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/26/1999 |
| From: | Nerses V NRC (Affiliation Not Assigned) |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| GL-95-07, GL-95-7, TAC-M93528, TAC-M93529, NUDOCS 9906070157 | |
| Download: ML17164B059 (9) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 26, 1999 Mr. Robert G. Byram Senior Vice President-Generation and Chief Nuclear Officer PP&L, Inc.
2 North Ninth Street Allentown, PA 18101 SUBJECT'EQUEST FOR ADDITIONALINFORMATION-GENERIC LETTER 95-07, "PRESSURE-LOCKING AND THERMAL-BINDINGOF SAFETY-RELATED POV/ER-OPERATED GATE VALVES,"SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (TAC NOS. M93528 AND M93529)
Dear Mr. Byram:
On August 17, 1995, the Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 95-07, "Pressure-Locking and Thermal-Binding of Safety-Related Power-Operated Gate Valves,"
to request that licensees take actions to ensure that safety-related power-operated gate valves that are susceptible to pressure locking or thermal binding are capable of performing their safety functions.
In a letter of February 13, 1996, you submitted your 180-day response to GL 95-07 for Susquehanna Steam Electric Station, Units 1 and 2. The NRC staff reviewed your submittal and requested additional information in a letter dated June 10, 1996.
In a letter of July 11, 1996, you provided the additional information. In letters of November 7, 1996, April29, 1997, and July 1, 1998, you supplemented your 180-day response.
After reviewing your GL 95-07 submittals for Susquehanna Steam Electric Station, Units 1 and 2, the staff has determined that further information is necessary to complete its safety evaluation.
Enclosed is a request for additional information (RAI). In an April28, 1999, telecon
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~ R. Byram with representatives of your staff (Coddington, et al.), the NRC staff discussed this information and obtained agreement that PP8L, Inc., would provide the information requested within 90 days upon receipt of this letter.
Ifyou have any questions, contact me a t (301) 415-1484.
~ Sincerely, victor Nerses,%r.
l roiect Manager, Section 1
Project Directorate I
Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
Docket File PUBLIC PDI-1 R/F S. Black M. O'rien V. Nerses S. Bajwa OGC ACRS A. Blough, RGN-I DOCUMENT NAME: O'EPDI-1ESUSQERAI93528.WPD To receive a copy of this document.
indicate in the box:
"C" - Copy without attachment/enclosure attachment/enclosure "N" - No copy "E" - Copy with OFFICE NAHE DATE PDI-I/P VNerses:lcc 05/P @99 PDI-2/LA HO'Brie 05/
99 PDI-I/SC SBajwa 05/
99 05/
" /99 OFFICIALRECORD COPY
F
R. Byram with representatives of your staff (Coddington, et al.), the NRC staff discussed this information and obtained agreement that PP&L, Inc., would provide the information requested within 90 days upon receipt of this letter.
Ifyou have any questions, contact me a t (301) 41 5-1 484.
~ Sincerely, victor Nerses,wr.
I raiect Manager, Section 1
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
Docket File PUBLIC PDI-1 R/F S, Black M. O'rien V. Nerses S. Bajwa OGC ACRS A. Blough, RGN-I DOCUMENT NAME: GAPDI-1ESUSQ)RAI93528.WPD To receive a copy of this document, indicate in the box:
C" - Copy without attachment/enclosure attachment/enclosure "N" - No copy "E" - Copy with OFFICE PDI-1/P VNerses:lcc PDI-2/LA NO'Brie PDI-I/SC SBajwa DATE 05/P @99 05/
99 05/
99 OFFICIALRECORD COPY 05/
/99 with representatives of your staff (Coddington, et ai.), the NRC staff discussed this information and obtained agreement that PP8L, Inc., would provide the information requested within 90 days upon receipt of this letter.
Ifyou have any questions, contact me a t (301) 415-1484.
Sincerely, Victor Nerses, Sr. Project Manager, Section 1
Project Directorate I
Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosure:
Request for Additional Information cc w/enc1: See next page
Susquehanna Steam Electric Station, Units 1 &2 Bryan A. Snapp, Esq.
Assoc. General Counsel PP&L, Inc.
2 North Ninth Street, GENTW3 Allentown, PA 18101-1179 Terry L. Harpster Manager - Nuclear Licensing PP&L, Inc.
2 North Ninth Street, GENA61 Allentown, PA 18101-1179 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 35, NUCSA4 Berwick, PA 18603-0035 Director-Bureau of Radiation Protection Pennsylvania Department of Environmental Protection P.O. Box 8469 Harrisburg, PA 17105-8469 Richard W. Osborne Allegheny Electric Cooperative, Inc.
212 Locust Street P.O. Box 1266 Harrisburg, PA 17108-1266 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Aliendale Road King of Prussia, PA 19406 Robert F. Saunders Vice President-Nuclear Site Operations Susquehanna Steam Electric Station Box 467, NUCSA4 Berwick, PA 18603-0035 Mr. Herbert D. Woodeshick Special Office of the President PP&L, Inc.
Rural Route 1, Box 1797 Berwick, PA 18603-0035 George T. Jones Vice President-Nuclear Engineering & Support PP&L, Inc.
2 North Ninth Street, GENA61 Allentown, PA 18101-1179 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 Board of Supervisors Salem Township P.O. Box 405 Berwick, PA 18603-0035
REQUEST FOR ADDITIONALINFORMATION SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 RESPONSE TO GENERIC LETTER 95-07 "PRESSURE-LOCKING ANDTHERMAL-BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES"
, he PP8L, Inc., response to Generic Letter (GL) 95-07 dated July 11, 1996, states that the reactor core isolation cooling (RCIC) suppression pool suction valves, HV-1(2)49-F031, were not inciuded in the scope of GL 95-07 because operation of the RCIC system is not classified as safety-related.
Valves HV-1-49-F031 and HV-2-49-F031 are normally closed and open to realign the suction of the RCIC from the condensate storage tank to the suppression pool. The response also states that these valves are included in your GL 89-10, "Safety-Related Motor-Operated Valve Testing and Surveillance," Program.
Supplement 6 to GL 89-10 addresses thermal binding and pressure locking of valves and recommends that licensees take corrective actions to ensure operability of those valves. The NRC, staff considers the criteria for identifying valves within the scope of GL 95-07 to be consistent with the scope criteria for GL 89-10. These valves are also included in your Inservice Test Program as having an open safety position.
I GL 95-07 states that licensees may need to evaluate potential pressure locking or thermal binding for other valves outside the scope of the GL based on previous licensing commitments.
Discuss any commitments that were made to the NRC when justifying the classification of the RCIC system as nonsafety-related.
This discussion should include the following items:
a.
Compliance with relevant standards which should assure the continuing ability of the RCIC system to function as required.
b.
How reliabilityof the RCIC system is affected by the nonsafety-related classification and ifa high level of confidence is required for the RCIC system to fulfillits design requirements.
c.
Iftechnical specification and inservice testing operability requirements are'effected by the nonsafety-related classification.
2.
Ifthe RCIC suppression pool valves willnot be included in the scope of GL 95-07, discuss how pressure-locking and thermal-binding of these valves affect overall risk to the plant. Ifapplicable, discuss any short-term corrective action to ensure operability if long-term corrective action is not complete.
Enclosure
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