U-602680, Submits Supplement to 960815 Application to Amend License NPF-62,requesting Rev to TS Re Safety Limit Minimum Critical Power Ratio Calculated by General Electric for Operating Cycle 7,in Response to NRC RAI
| ML20133F197 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 01/07/1997 |
| From: | Connell W ILLINOIS POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20133F201 | List: |
| References | |
| U-602680, WC-009-97, WC-9-97, NUDOCS 9701140103 | |
| Download: ML20133F197 (4) | |
Text
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Chnton Power Station P.o. Box 678 j~
Clinton,IL 61727 Tel 217 935 5623 Fax 217 935-4632 4
i Wilfred Connell Vice President i
ILLIN915 u-6o26so P49WER se.iooa i
wc-009-97 January 7, 1997 Docket No. 50-461 10CFR50.90 j
Document Control Desk j
Nuclear Regulatory Commission
. Washington, D.C. 20555 1
i
Subject:
Clinton Power Station - Supplement to Proposed
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Amendment of Facility Operating License No. NPF-62 (NS-96-004)
I Dear Madam or Sir.
By letter dated August 15,1996, [ Illinois Power (IP) letter U-602624], IP submitted an 7
application for amendment of Facility Operating License No. NPF-62, Appendix A - Technical
,i Specifications, for Clinton Power Station (CPS). The proposed amendment, currently under review by the NRC staff, consists of a change to the Technical Specifications to incorporate a 4
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revised Safety Limit Minimum Critical Power Ratio (SLMCPR) calculated by General Electric i
(GE) for CPS Operating Cycle 7. The need to change the SLMCPR resulted from the 10CFR l
Part 21 condition reported by GE in their letter to the NRC dated May 24,1996 (wherein it was identified that the generic SLMCPR calculated by GE in accordance with its standard methodology may not be conservative when applied to some actual core / fuel designs). IP's application for amendment was followed by two NRC requests for additional information to i.
which IP responded via letters U-602651 dated October 28,1996 and U-602662 dated l
November 15,1996.
l The proposed change to the CPS Technical Specifications described in IP's August 15,
- 1996 application for amendment is to revise the values specified for the MCPR Safety Limits in j
Technical Specification 2.1.1.2 for both normal (double) reactor recirculation loop operation i
and single recirculation loop operation. IP's submittal describes how, as an immediate action
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in response to the 10CFR Part 21 issue, GE calculated plant-specific SLMCPR values for CPS I
j (as well as for other plants) based on actual core loadings, projected control blade patterns, i
etc., for Operating Cycle 7 at CPS. IP noted that these cycle-specific values are to replace the values currently specified in the CPS Technical Specifications which were derived by GE in 1
accordance with its standard methodology (i.e., General Electric Standard Application for 4
' Reactor Fuel (GESTAR), NEDE-24011-P-A).
1
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I 9701140103 970107 PDR ADOCK 05000461 P
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5 U-602680 Page 2 of 3 f
Recent discussion with the NRC has determined that additional, minor changes should l
be made to the Technical Specifications in support ofIP's requested change for revising the li SLMCPR values. Specifically, the NRC has requested the following two changes:
(1)
Where the new values are to be incorporated into Technical Specification 2.1.1.2, a l
note should be added to clearly indicate that the specified SLMCPR values (as I
proposed) are only applicable for Cycle 7 operation.
(2)
Under Technical Specification 5.6.5, " Core Operating Limits Report (COLR)," where the basis for the COLR and controls on the core operating limits are described,
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another clarifying note should be added to acknowledge the fact that the proposed SLMCPR values were derived in a manner different than what was previously done j
under GE's standard methodology (which had been previously accepted by the NRC but which is now under review as a result of the 10CFR Part 21 issue). Specifically, where it is stated, "The analytical methods used to determine the core operating limits i
shall be those previously reviewed and approved by the NRC in General Electric Standard Application for Reactor Fuel (GESTAR), NEDE-24011-P-A, (latest l
approved version)," the parenthetical phrase " latest approved version" should be replaced with the following exception: "...except that the MCPR Safety Limits for 1
Operating Cycle 7 shall be determined as described in Illinois Power letters (to the NRC) U-602624 dated August 15,1996.; U-602651 dated October 28,1996; and U-602662 dated November 15, 1996."
The above-described changes are reflected on a marked-up copy of the affected pages from the CPS Technical Specifications, provided as Attachment 2 to this submittal. Double-revision bars have been used to identify these changes so that they may be distinguished from the changes indicated in IP's August 15,1996 submittal. (For convenience, the changes addressed by IP's August 15 submittal are included in Attachment 2 and are indicated via single-revision bars.) In addition to Attachment 2, an affidavit supporting the facts set forth in this letter is provided as Attachment 1.
With respect to no significant hazards and environmental impact considerations, the changes described in this submittal support the changes proposed in IP's August 15,1996 appliation for amendment. The changes in this submittal are merely administrative and are proposed for clarification purposes relative to the substantive, technical changes proposed in the August 15 submittal. Therefore, these proposed changes do not alter the Basis for No Significant Hazards Determination provided in IP's August 15 submittal, and IP has determimd that the No Significant Hazards Determination presented in the August 15 submittal remains valid and bounds the changes described herein. Similarly, IP has also determined that the changes proposed herein, when evaluated against the criteris of 10CFR51.22, may be categorically excluded from the requirement for an Environmental Impact Statement,just as concluded for the changes described in IP's August 15 submittal.
i ImammmMa 4
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i 2-U-602680 Page 3 of 3 t
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In response to comments from the NRC, tlt's submittal supplements and supports IP's application for amendment of the CPS Operating License. As discussed previously with the NRC staff, issuance of the amendment is required to support restart from the current outage for entry into Operating Cycle 7, including issuance of the Core Operating Limits Report for Cycle 7. This letter is therefore respectfully submitted with the expectation that it will j
expedite approval ofIP's application for amendment.
d Sincerely yours,
.Q 1
Wilfred Connell N
Vice President k
TBE/krk 1
Attachments l
cc:
NRC Clinton Licensing Project Manager
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NRC Resident Office, V-690 j
ilegic al Administrator, Region III, USNRC j
Illinois Department ofNuclear Safety I
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Attichment I to U-602680 Richard F. Phares, being first duly sworn, deposes and says: That he is Manager-Nuclear Assessment ofIllinois Power; that this supplement to the proposed amendment ofFacility Operating License No. NPF-62 (LS-94-013) has been prepared under his supervision and direction; that he knows the contents thereof; and that to the best of his knowledge and belief said letter and the facts contained therein are true and correct.
l Date: This 7" day ofJanuary 1997.
Signed: _
Richard F. Phares STATE OF ILLINOIS l
f
_le& h COUNTY J
Subscribed and sworn to before me this Y day ofJanuary 1997.
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