ML20149F984
| ML20149F984 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/23/1994 |
| From: | Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20149F990 | List: |
| References | |
| NUDOCS 9409290232 | |
| Download: ML20149F984 (4) | |
Text
l Ct: tion cupport Dep:rtment m
PECO ENERGY ecco '"e'o< c ea "<
Nuclear oroup Headquarters 965 Chesterbrook Boulevard Wayne, PA 19087-5691 September 23,1994 D-
' ?t Nos. 50-352 50-353 License Nos. NPF-39 NPF-85 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
Limerick Generating Station, Units 1 and 2 Technical Specifications Change Request No. 94-11-0 Response to Requests for AdditionalInformation Gentlemen:
By letter dated July 20,1994, PECO Energy Company submitted Limerick Generating Station (LGS), Unit I and Unit 2. Technical Specifications (TS) Change Request No. 94-11-0 which proposed to raise the Steam Leakage Temperature Set-points that isolate the HPCI and RCIC System Equipment. On September 8,1994, a presentation was made by PECO Energy at the NRC's Headquarters in Rockville, Maryland, supporting TS Change Request No. 94-11-0. The NRC requested additional information, during the presentation, which is provided in Appendix 1.
This additional information is being submitted under affirmation, and the associated affidavit is
- enclosed, if you have any questions, please do not hesitate to contact us.
h'! truly yours,
-l
,7 G. A. Hunger, Jr.,
Director - Licensing Attachments Enclosure cc:
T. T. Martin, Administrator, Region I, USNRC (w/ attachments and enclosure)
N. S. Perry, USNRC Senior Resident inspector, LGS (w/ attachments and enclosure)
R. R. Janati, PA Bureau of Radiological Protection (w/ attachments and enclosure) b b][ ( 5.I 8
9409290232 940923 PDR ADOCK 05000352 l
p PDR
COMMONWEALTH OF PENNSYLVANIA I
ss.
COUNTY OF CHESTER l
W. H. Smith, Ill, being first duly sworn, deposes and says: That he is Vice President of PECO Energy Company, the Applicant herein; that he has read the enclosed Request for Additional Information supporting Technical Specifications Change Request No. 94-11-0 ' Raising the Steam Leakage Detection System Set-points that isolate the High Pressure Coolant injection (HPCI) System and Reactor Core Isolation Cooling (RCIC) System Equipment on Equipment Room High Temperature and High Delta Temperature," for Limerick Generating Station, Unit 1 and Unit 2, Facility Operating License Nos. NPF-39 and NPF-85, and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.
Vice Pres Subscribed and sw to befo e me this day a
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Notary Public Ence A Santon,Notafy PLNC My Op 4 E
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I ATTACHMENT 1 LIMERICK GENERATING STATION UNIT 1 AND UNIT 2 DOCKET NOs.
50-352 50-353 LICENSE NOs.
NPF-39 NPF-85 TECHNICAL SPECIFICATIONS CHANGE REQUEST NO. 94-11-0 REOUEST FOR ADDITIONAL INFORMATION
" Raising the Steam Leakage Detection System Set-points that Isolate the High Pressure Coolant injection (HPCI) System and Reactor Core isolation Cooling (RCIC) System Equipment on Equipment Room High Temperature and High Delta Temperature."
Additional Information Supporting Change - 2 pages l
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v3 PAGE1 On Thursday, September 8,1994, at the NRC's Headquarters in Rockville, Maryland, PECO Energy made a presentation associated with Limerick Licensing changes involving Technical Specifications Change Request No. 94-11-0, " Raising the Steam Leakage Detection System Set-points that isolate the HPCI System and RCIC System Equipment on Equipment Room High Temperature and High Delta Temperature." During the September 8,1994 presentation the NRC asked PECO Energy to provide responses to the following questions.
1.
Are there any radiation monitors in the HPCI and RCIC Equipment Compartments?
Resoonse:
Yes. As shown in the Updated Final Safety Analysis Report, table 12.3-7, page 1, both the HPCI and RCIC Equipment Compartments have area Radiation Monitoring System Equipment.
2.
What does the HPCI Equipment Compartment Temperature Profile look like while the HPCI System is operating under it's Design Basis condition? What model was used to obtain this profile?
Resoonse:
The HPCI and RCIC Equipment Comptrtment Temperature Profile graph is attached. The Bechtel computer program PCFLUD was used to obtain this profile. PCFLUD program is used to calculate pressure and temperature transients in nuclear power plant structures which are -
subject to hypothetical pipe break accidents. It is used to calculate long term temperature transients resulting from pipe breaks or loss of room cooling It can be used to model the effects of ventilation fans on the environmental temperature and pressure in a room. PCFLUD has not been approved by the NRC under a topical report. However, the code has been reviewed by the NRC during licensing reviews for several plants; the most recent review was during the licensing of Vogtle. The two predecessor codes to PCFLUD were COPATTA and COPDA, which were approved, as topical reports, by the NRC. PCFLUD has been benchmarked against these preceding codes and validated and verified in accordance with Bechtel's OA plan.
3.
What equipment, in the HPCI Equipment Compartment, will still be required to operate following a HPCI System leak?
Resoonse:
The only equipment located in the HPCI Equipment Compartment which will be required to function post leak are the Steam Leak Detection System temperature sensors. These sensors have been qualified for 450 *F.
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