ML20207L656
| ML20207L656 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/11/1999 |
| From: | Geoffrey Edwards PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20137A820 | List: |
| References | |
| NUDOCS 9903180212 | |
| Download: ML20207L656 (6) | |
Text
A 10 CFR 50.90 PECO NUCLEAR esco c-c-n.ev Nuclear Group Headquarters A Unit of PECO Energy 965 Chesterbrook Boulevard Wayne. PA 19087-5691 March 11,1999 Docket No. 50-353 License No. NPF-85 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Limerick Generating Station Unit 2 Technical Specifications Change Request No. 98-07-2
Dear Sir / Madam:
PECO Energy Company is submitting Technical Specifications (TS) Change Request No. 98 2, in accordance with 10 CFR 50.90, requesting an amendment to the TS (Appendix A) of Operating License No. NPF-85 for Limerick Generating Station (LGS), Unit 2. This proposed change will revise TS Section 2.1, " Safety Limits," to revise the Minimum Critical Power Ratio (MCPR) Safety Limit. Information supporting this TS Change Request is contained in Attachment 1 to this letter, and the proposed TS pages (including marked-up pages) showing the proposed changes to the LGS Unit 2 TS are contained in Attachment 2. This information is being submitted under affirmation, and the required affidavit is enclosed., letter from R.M. Butrovich (GE) to K.W. Hunt (PECO), " Limerick Unit 2, Cycle 6 Safety Limit MCPR," dated February 4,1999, specifies the new MCPR Safety Limits for LGS Unit 2, Cycle 6. Attachment 3 contains information proprietary to GE. GE requests that the document be withheld from public disclosure in accordance with 10 CFR 2.790(a)(4). An affidavit supporting this request in accordance with 10 CFR 2.790(b)(1) is provided with Attachment 3. contains the non-proprietary version of Attachment 3.
We request that, if approved, the TS change proposed herein be issued by April 26,1999, and become effective within 30 days of issuance in order to support LGS Unit 2 start-up.
If you have any questions, please do not hesitate to contact us.
\\
Very truly yours, jd e
arrett D. Edwards g00@
D.
Director-Licensing
Enclosures:
Attachments; Affidavit cc:(w/ enc)
H. J. Miller, Administrator, Region 1, USNRC A. L. Burritt, USNRC Senior Resident inspector, LGS R. R. Janati, PA Bureau of Radiological Protection CPME: b oui#9 POR i
9903190212 990311 PDR ADOCK 05000353 P
COMMONWEALTH OF PENNSYLVANIA.
- ss.
COUNTY OF CHESTER J. J. Hagan, being first duly swom, deposes and says:
That he is Ser.ior Vice President of PECO Energy Company, the Applicant herein; that he has read the foregoing Application for Amendment of Facility Operating License No. NPF-85 l
(Technical Specifications Change Request No. 98-07-2), to change the Minimum Critical Power i
Ratio (MCPR) Safety Limits at Limerick Generating Station, Unit 2, and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of j
his knowledge, information and belief.
A; r Vice es dent Subscribed and swom to before me this /ON day of 1999.
/
Notary /ublic i
MM $9.I Carol A.
Notary Putsc w!:21%.N"b
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ATTACHMENT 1 f
LIMERICK GENERATING STATION UNIT 2 DOCKET NO. 50-353 LICENSE NO. NPF-85 l
l TECHNICAL SPECIFICATIONS CHANGE REQUEST NO. 98-07-2 Supporting information for Change - 3 Pages
" MINIMUM CRITICAL POWER RATIO (MCPR) SAFETY LIMIT REVISION" o
March 11,1999 Docket No. 50-353 License No. NPF-85 Page 1 of 3 introduction i
PECO Energy Company, Licensee under Facility Operating License No. NPF-85 for the Limerick Generating Station (LGS), Unit 2, requests that the Technical Specifications (TS) contained in Appendix A to the Operating License be amended to revise TS Section 2.1 and its associated TS Bases to reflect changes in the Minimum Critical Power Ratio (MCPR) Safety Limits due to the use of cycle specific analysis performed by General Electric Nuclear Energy (GENE) for LGS, Unit 2, Cycle 6. The proposed changes to the LGS Unit 2 TS are indicated by markups on TS page 2-1 and TS Bases page B 2-1. The TS page and TS Bases page showing the proposed changes are contained in Attachment 2. (Letter from R.M. Butrovich (GENE) to K.W. Hunt (PECO Energy), " Limerick Unit 2, Cycle 6 Safety Limit MCPR," dated February 4,1999 specifies the new MCPR Safety Limits for LGS, Unit 2, Cycle 6.
We request that, if approved, the TS changes proposed herein be issued by April 26,1999, and become effective within 30 days of issuance in order to support LGS Unit 2 startup.
This License Change Application provides a discussion and description of the proposed TS changes, a safety assessment of the proposed TS changes, information supporting a finding of i
No Significant Hazards Consideration and information supporting an Environmental Assessment.
Discussion and Description of the Proposed Chanoes The proposed Technic.sl Specifications (TS) Change Request involves the change of Limerick Generating Station (LG t "Init 2, TS Section 2.1 and its associated TS Bases to revise the Minimum Critical Powe' A mo (MCPR) Safety Limits., Letter from R.M. Butrovich (GENE) to K.W. Hunt (PECO Energy), " Limerick Unit 2, Cycle 6 Safety Limit MCF R," dated February 4,1999, specifies the new MCPR Safety Limits i
for LGS, Unit 2, Cycle 6. The new MCPR Safety Limits are calculated using NRC-approved methods (i.e., GESTAR-II, Rev.13). The calculation inputs include the following cycle-specific parameters: the actual core design; projected control blade patterns; the actual bundle parameters; and the full (,ycle exposure range. The MCPR Safety Limit is set high enough to l
ensure that greater than 99.9 percent of all fuel rods in the core are expected to avoid transition boiling if the limit is not violated. The resu',.s of the GE analysis for LGS, Unit 2, Cycle 6 show a MCPR Safety Limit of 1.12 for two loop operation, and 1.14 for single loop operation.
Therefore, we propose that LGS Unit 2, TS Section 2.1 and TS Bases 2.1 be revised to reflect the change in the Minimum Critical Power Ratio (MCPR) Safety Limits for LGS, Unit 2, Cycle 6.
C
March 11,1999 Docket No. 50-353 License No NPF-85 Page 2 of 3 Safety Assessment The proposed TS changes will revise TS Section 2.1 and its associated TS Bases to reflect the change in the Minimum Critical Power Ratio (MCPR) Safety Limits, due to the plant specific evaluation performed by General Electric Co. (GE) for LGS, Unit 2, Cycle 6.
The new MCPR Safety Limits are calculated using NRC-approved methods (i.e., GESTAR-ll, Rev.13). The calculation inputs include the following cycle-specific parameters: the actual core design; projected control blade patterns; the actual bundle parameters; and the full cycle exposure range. The MCPR Safety Limit is set high enough to ensure that greater than 99.9 percent of all fuel rods in the core avoid transition boiling if the limit is not violated. The new MCPR Safety Limit for LGS, Unit 2, Cycle 6 is 1.12 for operation with two recirculation loops and 1.14 for single loop operation.
Information Supportina a Findina of No Sionificant Hazards Consideration We have concluded that the changas to the Limerick Generating Station (LGS) Unit 2 Technical Specifications (TS), which will revise TS Section 2.1, " Safety Limits," and its associated TS 4
Bases to chance the Minimum Critical Power Ratio (MCPR) Safety Limits, do not involve a Significant Hazards Consideration. In support of this determination, an evaluation of each of the three (3) standards set forth in 10 CFR 50.92 is provided below.
- 1. The proposed TS chances do not involve a significant increase in the probability or consecuences of an accident previous:v evaluated.
The revised MCPR Safety Limits for LGS Unit 2 Technical Specifications, and their use to i
detent ne cycle-specific thermallimits, have been calculated using NRC-approved methods (i. e, GESTAR-II, Rev.13) and are based on LGS, Unit 2, Cycle 6 specific inputs. The use of these methods assures that tho SLMCPR value is within the existing design and licensing basis, and cannot increase the probability or severity of an accident.
i The basis for the MCPR Safety Limit calculation is to ensure that greater than 99.9 percent of all fuel rods in the core avoid transition boiling if the limit is not violated. The MCPR Safety Limit preserves the existing margin to transition boiling and fuel damage in the event of a postulated accident. The probability of fuel damage is not increased.
Therefore, the proposed TS changes do not involve an increase in the probability or consequences of an accident previously evaluated.
O
March 11,1999 Docket No. 50-353 License No. NPF-85 Page 3 of 3 1
- 2. The proposed TS chanaes do not create the possibility of a new or different kind of accident from any accident oreviousiv evaluated.
The MCPR Safety Limit is a Technical Specification numerical value designed to ensure that fuel damage from transition boiling does not occur as a result of the limiting postulated accident. The MCPR Safety Limit is not an accident initiator; therefore, it cannot create the possibility of any new type of accident. The new MCPR Safety Limits are calculated usi~
i l
NRC-approved methods (i.e., GESTAR-II, Rev.13) and are based on LGS, Unit 2, Cycle 6 specific inputs.
Therefore, the proposed TS changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
i
- 3. The proposed TS chanaes do not involve a sianificant reduction in the marain of safel The margin of safety as defined in the TS Bases will remain the same. The new MCPR Safety Limits are calculated using NRC-approved methods (i.e., GESTAR-II, Rev.13),
which are in accordance with the current fuel design and licensing criteria, and are based on LGS, Unit 2, Cycle 6 specific inputs. The MCPR Safety Limit remains high enough to ensure that greater than 99.9 percent of all fuel rods in the core will avoid transition boiling if l
the limit is not violated, thereby preserving the fuel cladding integrity.
Therefore, the proposed TS changes do not involve a reduction in the margin of safety.
I Information Succortina an Environmental Assessmeni An Environmental Assessment is not required for the changes proposed by this TS Change Request because the requested changes to the Limerick Generating Station (LGS), Unit 2 TS conferm to the criteria for " actions eligible for categorical exclusion" as specified in 10 CFR 51.22 (c)(9). The requested changes will have no impact on the environment. The proposed l
changes do not involve a significant hazards consideration as discussed in the preceding section. The proposed changes do not involve a significant change in the types, or a significant increase in the amounts, of any effluents that may be released offsite. In addition, the proposed changes do not involve a significant increase in individual or cumulative occupational radbtion exposure.
Conclusion The Plant Operations Review Committee and the Nuclear Review Board have reviewed these proposed changes to the Limerick Generating Station (LGS), Unit 2 TS and have concluded that they do not involve an unreviewed safety question, and will not endanger the health and safety of the public.
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