ML17157A779
| ML17157A779 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/30/1991 |
| From: | Raleigh J Office of Nuclear Reactor Regulation |
| To: | Keiser H PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| TAC-80105, TAC-80106, NUDOCS 9108070018 | |
| Download: ML17157A779 (7) | |
Text
July 30, 1991 Docket Nos. 50-387 and 50-388 Mr. Harold W. Keiser Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Al1 entown, Pennsylvania 18101
Dear Mr. Keiser:
DISTRIBUTION
~n NRC IlA Local PDRs PDI-2 Reading SVarga JCalvo MO'Brien(2)
JRaleigh OGC
- EJordan, 3701
- JTatum, 8D-1
- RBlough, RGN-I
- JWhite, RGN-I
SUBJECT:
PROPOSED REVISIONS TO THE SUSQUEHANNA STEAM ELECTRIC STATION TECHNICAL SPECIFICATION REQUIREMENTS RELATED TO THE TEMPERATURE LEAK DETECTION ISOLATION FUNCTION IN THE RHR ROOM (TAC NOS. 80105 AND 80106)
The staff has reviewed the request that was made by Pennsylvania Power and Light Company (PPIEL or the licensee) of January 14, 1991, related to the elimination of the temperature leak detection isolation function (ambient and differential) in the RHR pump rooms for Susquehanna Steam Electric Station (SSES),
Units 1 and 2.
Based on this review, we have concluded that sufficient information and justification to support the proposed changes to the SSES Technical Specification (TS) requirements has not been provided.
As a result of the review, the staff has developed comments which form the basis of this request for additional information.
These comments are provided in the enclosure.
This matter was discussed with the licensee in a telephone conversation on July 3, 1991.
If there are any question regarding this letter please contact me on (301) 492-1447.
This requirement affects fewer than 10 respondents and, therefore, is not subject to Office of Management and Budget review under P.L.96-511.
S incere ly, 9108070018 910730 POR ADQCK 05000387 P
Enclosure:
Request for Additional Information cc w/enclosures:
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James J. Raleigh, Acting Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
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Docket Nos.
50-387 and 50-388 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555 July 30, 1991 Mr. Harold kl. Keiser Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Al 1 entown, Pennsy 1vani a 18101
Dear Mr. Keiser:
SUBJECT:
PROPOSED REVISIONS TO THE SUSQUEHANNA STEAM ELECTRIC STATION TECHNICAL SPECIFICATION REQUIREMENTS RELATED TO THE TEMPERATURE LEAK DETECTION ISOLATION FUNCTION IN THE RHR ROOM (TAC NOS.
80105 AND 80106)
The staff has reviewed the request that was made by Pennsylvania Power and Light Company (PP&L or the licensee) of January 14, 1991, related to the elimination of the temperature leak detection isolation function (ambient and differential) in the RHR pump rooms for Susquehanna Steam Electric Station (SSES),
Units 1 and 2.
Based on this review, we have concluded that sufficient information and justification to support the proposed changes to the SSES Technical Specification (TS) requirements has not been provided.
As a result of the review, the staff has developed comments which form the basis of this request for additional information.
These comments are provided in the enclosure.
This matter was discussed with the licensee in a telephone conversation on July 3, 1991.
If there are any question regarding this letter please contact me on (301) 492-1447.
This requirement affects fewer than 10 respondents and, therefore, is not subject to Office of Management and Budget review under P.L.96-511.
S in cere ly,
Enclosure:
Request for Additional Information cc w/enclosures:
See next page J
mes J. Raleigh, Acting Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Mr. Harold W. Keiser Pennsylvania Power
& Light Company Susquehanna Steam Electric Station Units 1
& 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 Mr. J.
M. Kenny Licensing Group Supervisor Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Scott Barber Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O.
Box 35 Berwick, Pennsylvania 18603-0035 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Resources Commonwealth of Pennsylvania P. 0.
Box 2063 Harri sburg, Pennsylvania 17120 Mr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.
212 Locust Street P.O.
Box 1266 Harrisburg, Pennsylvania 17108-1266 Mr. S.
B. Ungerer Joint Generation Projects Department Atlantic Electric P.O.
Box 1500 1199 Black Horse Pike Pleasantville, New Jersey 08232 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. Harold G. Stanley Superintendent of Plant Susquehanna Steam Electric Station Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company 1009 Fowles Avenue Berwi ck, Pennsylvania 18603 Mr.'obert G.
Byram Vice President-Nuclear Operations Pennsylvania Power and Light Company 2 North Ninth Street Al 1 entown, Pennsy1vani a 18101
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED REVISIONS TO THE SUSQUEHANNA STEAN ELECTRIC STATION TECHNICAL SPECIFICATION REQUIREMENTS RELATED TO THE TEMPERATURE LEAK DETECTION ISOLATION FUNCTION IN THE RHR PUMP ROOMS DOCKET NOS.
50-387 AND 50-388 Pennsylvania Power and Light Company (PP&L or the licensee)'equested NRC review and approval of a proposed change to the Technical Specification requirements related to elimination of the ambient and differential temperature leak detection isolation function in the RHR pump room for the Susquehanna Steam Electric Station (SSES), Unit Nos.
1 and 2, by letter of January 14, 1991.
The staff has completed a preliminary review of the licensee's request and based on that review, the staff has identified the following comments and questions for consideration.
The licensee is requested to revise its submittal according ly.
1.
The licensee has had previous discussions with the staff regarding this matter and for completeness, the submittal should make reference to these discussions and should include a summary of the major points of discussion and any conclusions that were reached.
n C. ~
It is not clear why it is necessary to delete the isolation function.
This should be explained in detail.
Also, are other options available, such as enabling the isolation function only for periods when the RHR system is not isolated from the reactor coolant system and/or establishing a higher leak rate as the basis for isolation' 3.
The staff's copy of the FSAR for Susquehanna has not been updated for some time and the information regarding RHR operation may not be current.
In order to facilitate the staff's review, a detailed description of the RHR system and operating modes should be provided.
4.
Details of the RHR pump room temperature analysis should be provided for staff review.
Detailed information related to the application of computer codes should also be provided unless the staff has previously reviewed and approved the code for the specific application in question.
In any case, all assumptions used in the analysis should be identified and fully explained.
5.
The licensee has discussed actions that can be taken in lieu of the automatic isolation function, but a complete description of specific actions that will be required and how these requirements will be implemented has not been provided for staff review.
The qualification, quality classification, surveillance requirements and single-failure aspects of equipment such as the sump level instrument and annunciators have not been discussed and it is not clear to what extent this equipment can be relied upon to function.
Additionally, there was no discussion relative to ASME Code requirements and how these requirements would be satisfied.
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6.
The licensing basis assumes that leaks from the reactor coolant system will be isolated in a short period of time.
Without the automatic isolation capability in place, a detailed analysis of the radiological consequences of a coolant leak outside primary containment must be completed and submitted for staff review.