ML18030A428
| ML18030A428 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/08/1998 |
| From: | Nerses V NRC (Affiliation Not Assigned) |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| TAC-MA0340, TAC-MA0341, TAC-MA340, TAC-MA341, NUDOCS 9807130269 | |
| Download: ML18030A428 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 8, 1998 Mr. Robert G. Byram Senior Vice President-Generation and Chief Nuclear Officer Pennsylvania Power and Light Company 2 North Ninth Street Allentown, PA 18101
SUBJECT:
REQUEST FOR ADDITIONALINFORMATIONFOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND2, INSERVICE TESTING RELIEF REQUESTS (TAC NOS. MA0340 AND MA0341)
Dear Mr. Byram:
On November 14, 1997, you submitted a revised relief request in response to NRC's safety evaluation (SE) dated July 17, 1997, for the Susquehanna Steam Electric Station, Units 1 and 2, inservice testing program.
NRC's SE dated July 17, 1997, denied an earlier relief request RR-15 following your submittals dated August 4, 1995, April23, and May 6, 1996.
Prior to this denial, RR-15 had been granted in NRC's SE dated April26, 1995, for an interim period of one year or to the next refueling outage, whichever was later.
The staff has determined that additional information, as described below, is required in order to complete our review of this latest revision of RR-15.
Revised RR-15 states that establishing a single repeatable reference point required in OM-6, Paragraph 5.2, for the emergency condenser water circulating pumps, OP-171-AIB, is impracticable because (1) the pumps operate under a variety of flow rate and differential pressure conditions, and (2) a single repeatable reference point cannot be established without rendering a safety system inoperable.
Under these conditions, it appears that an alternative test method involving the use of pump curves is appropriate.
NUREG-1482, "Guidelines for Inservice Testing at Nuclear Power Plants," Section 5.2, "Use of Variable Reference Values for Flow Rate and Differential Pressure During Pump
'esting," provides the following guidelines:
(1)
Curves are developed, or manufacturers'ump curves are validated, when the pumps are known to be operating acceptably.
(2)
The reference points used to develop or validate the curve are measured using instruments at least as accurate as required by the Code.
(3)
Curves are based on an adequate number of points, with a minimum of five.
(4)
Points are beyond the "flat"portion (low flow rates) of the curve in a range which includes or is as close as practicable to design basis flowrates.
(5)
Acceptance criteria based on the curves do not conflict with Technical Specification or Facility Safety Anetysts Report operability criteria, for flow rate and differential pressure, f 0I for the affected pumps.
(6)
Ifvibration levels vary significantly over the range of pump conditions, a method for assigning appropriate vibration acceptance criteria should be developed for regions of the pump curve.
9807i30269 980708 PDR ADQCK 05000387 P
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R. Byram
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When the reference curve may have been affected by repair, replacement, or routine service, a new reference'curve willbe determined or the previous curve revalidated by an inservice test.
Discuss each of these seven elements and provide justification ifthe elements are not followed.
Ifa proposed alternative includes an enhanced periodic maintenance program, provide details of the program, iricluding the frequency of maintenance, and provide the basis for a finding that this proposed alternative willnot compromise the operational readiness of the pumps in question.
Sincerely, Docket Nos. 50-387 and 50-388
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Docket File PUBLIC PDI-2 Reading JZwolin ski RCapra MO'Brien VNerses OGC ACRS CAnderson, RGN I
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Victor Nerses, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation DATE
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When the reference curve may have been affected by repair, replacement, or routine service, a new reference curve willbe determined or the previous curve revaiidated by an inservice test.
Discuss each of these seven elements and provide justification ifthe elements are not followed.
If a proposed alternative includes an enhanced periodic maintenance program, provide details of the program, including the frequency of maintenance, and provide the basis for a finding that this proposed alternative willnot compromise the operational readiness of the pumps in question.
Sincerely, Docket Nos. 50-387 and 50-388 cc: See next page
/s/
Victor Nerses, Senior Project Manager Project Directorate 1-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation F
Docket File..
PUBLIC PDI-2 Reading JZwolinski RCapra MO'Brien VNerses OGC ACRS CAnderson, RGN I OFFICE NAME DATE P l2/ M V erses:mw
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R. Byram
-(7)
When the reference curve may have been affected by repair, replacement, or routine service, a new reference curve willbe determined or the previous curve revalidated by an inservice test.
Discuss each of these seven elements and provide justification if,the elements are not followed.
lfa proposed alternative includes an enhanced periodic maintenance program, provide details of the program, including the frequency of maintenance, and provide the basis for a finding that this proposed alternative willnot compromise the operational readiness of the pumps in question.
Sincerely, Docket Nos. 50-387 and 50-388 Victor Nerses, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - l/ll Office of Nuclear Reactor Regulation cc: See next page
Mr. Robert G. Byram Pennsylvania Power & Light Company Susquehanna Steam Electric Station, Units 1 &2 Jay Silberg, Esq.
Shaw, Pittman, Potts &Trowbridge 2300 N Street N.W.
Washington, D.C. 20037 Bryan A, Snapp, Esq, Assistant Corporate Counsel Pennsylvania Power & Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Licensing Group Supervisor Pennsylvania Power & Light Company 2 North Ninth Street Allentown, Pennsylvania I8I01 Regional Administrator, Region I U,S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 General Manager Susquehanna Steam Electric Station Pennsylvania Power and Light Company Box 467 Beiwick, Pennsylvania 18603 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company Rural Route 1, Box 1797 Benvick, Pennsylvania 18603 Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O. Box 35 Berwick, Pennsylvania 18603-0035 Director-Bureau of Radiation Protection Pennsylvania Department of Environmental Resources P. O. Box 8469 Harrisburg, Pennsylvania 17105-8469 Mr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.
212 Locust Street P.O. Box 1266 Harrisburg, Pennsylvania 17108-1266 George T. Jones Vice President-Nuclear Operations Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 Chairman Board of Supervisors 738 East Third Street Berwick, PA 18603