ML17164A776
| ML17164A776 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/08/1998 |
| From: | Nerses V NRC (Affiliation Not Assigned) |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| TAC-MA0342, TAC-MA342, NUDOCS 9809140123 | |
| Download: ML17164A776 (6) | |
Text
September 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 ADDITIONALINFORMATION(RAI) REGARDING CHANGE OF TECHNICALSPECIFICATION (TS) FOR ULTIMATEHEAT SINKAVERAGE TEMPERATURE FOR THE SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND2 (TAC NOS. MA0342 AND MA0343)
Dear Mr. Byram:
The NRC staff is currently reviewing the TS amendment request from Pennsylvania Power and Light Company (PP8L) dated June 1, 1998, for changing the ultimate heat sink average temperature surveillance requirement 3.7.1.2 from 88 'F to allow a graduated increase from 85 'F to 88 'F.
In order to complete its evaluation of the requested amendment, the NRC requests that you provide a response to the enclosed RAI. The contents of the enclosed RAI were discussed in a telephone call with Mr. M. Crowthers on September 4,1998, and it was agreed that PPBL would provide a response by October 21, 1998.
Ifyou have any questions regarding this request, please contact me at (301) 415-1484.
Sincrire)y, Victor Nerses, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosure:
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 20555-0001 September 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 ADDITIONALINFORMATION(RAI) REGARDING CHANGE OF TECHNICALSPECIFICATION (TS) FOR ULTIMATEHEAT SINKAVERAGE TEMPERATURE FOR THE SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND2 (TAC NOS. MA0342 AND MA0343)
Dear Mr. Byram:
The NRC staff is currently reviewing the TS amendment request from Pennsylvania Power and Light Company (PPSL) dated June 1, 1998, for changing the ultimate heat sink average temperature surveillance requirement 3.7.1.2 from 88 'F to allow a graduated increase from 85 'F to 88 'F.
In order to complete its evaluation of the requested amendment, the NRC requests that you provide a response to the enclosed RAI. The contents of the enclosed RAI were discussed in a telephone call with Mr. M. Crowthers on September 4, 1998, and it was agreed that PP8L would provide a response by October 21, 1998.
Ifyou have any questions regarding this request, please contact me at (301) 415-1484.
Sincerely, Docket Nos. 50-387 and 50-388
Enclosure:
RAI cc w/encl: See next page Victor Nerses, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Mr. Robert G. Byram Pennsylvania Power & Light Company Susquehanna Steam Electric Station, Units1 &2 CC:
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 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
..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 Berwick, Pennsylvania 18603 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company Rural Route 1, Box 1797 Berwick, Pennsylvania 18603 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 Mr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.
212 Locust Street P.O. Box 1266 Harrisburg, Pennsylvania 17108-1266 Board of Supervisors Salem Township P.O. Box 405 Berwick, PA 18603
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REQUEST FOR ADDITIONALINFORMATIONFOR TECHNICALSPECIFICATION CHANGE RELATEDTO ULTIMATEHEAT SINKAVERAGETEMPERATURE SUSQUEHANNA STEAM ELECTRIC STATION (SSES), UNITS 1 AND2 Currently the Technical Specification (TS) surveillance requirement (SR) 3.7.1.2 for SSES assures that the ultimate heat sink (UHS) average water temperature is maintained less than or equal to 88 'F. Pennsylvania Power and Light Company proposed to replace the above cited TS section, SR 3.7.1.2, with the following sections to allow a graduated increase in UHS temperature from 85 'F to 88 'F:
a.
SR 3.7.1.2.a When both units are in Mode 1 or 2, or either unit has been in Mode 3 for less than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, verify the average water temperature in the UHS is s 85 'F.
b.
SR 3.7.1.2.b When either unit has been in Mode 3 for at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> but not more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, verify the average water temperature in the UHS is s 87 'F.
I c.
SR 3.7.1.2.c When either unit has been in Mode 3 for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, verify the average water temperature in the UHS is z 88 'F.
In order to complete our review of the proposed TS amendment, the following additional information is requested:
1.
Discuss the analyses performed to demonstrate the impacts of the elevated average UHS.
water temperature on safety-related systems (i.e., shutdown cooling systems, emergency core cooling systems, containment systems, suppression pool, emergency diesel generators, etc.) for each of the above scenarios.
Information to be provided should also include existing containment (drywell and wetwell) design temperature and pressure and the calculated containment peak and long-term temperatures and pressures following a loss-of-coolant accident for the above scenarios.
2.
Discuss the procedures to be utilized by the SSES staff to monitor and control the UHS water temperature so as to remain within the design basis limiting values.
Discuss and justify the location of needed instrumentation for monitoring the average UHS temperature.
- Also, discuss the effects of UHS temperature instrument uncertainties on the systems and components that interface with the UHS.
Enclosure