ML20040B231
| ML20040B231 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 01/11/1982 |
| From: | Parker W DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20040B232 | List: |
| References | |
| NUDOCS 8201250290 | |
| Download: ML20040B231 (2) | |
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D IIK I? POWE H C(D11%NY l'owEu lit:: DINO 422 Sot: Tis Cstl'urit STittctcT, CitAHlOTTE, N. C. ariu42 WILLI AM O. PA R ur E A, J R, January 11, 1982 u,, 3 o.
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3 7 3-4 C 8 3 Mr. liarold R. Denton, Director CO g
Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 S
ggg5WED L11 Attention:
Ms. E. G. Adensam, Chief
- p gn 2 219829-Licensing Branch No. 4
,g m erz1L mn ny M M 1'2 Re: McGuire Nuclear Station W
Docket No. 50-369
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Dear Mr. Denton:
is a proposed change to the McGuire Nuclear Station Technical Specifications regarding boron concentration in the Boron Injection Tank.
The proposed change is for a period of 7 days commencing on January 11, 1982 and running through January 18, 1982.
It is requested that this change be expedited since severe power shortages are being experienced in the Southeast.
Expeditious granting of this request would permit McGuire to return to power to provide needed capacity during what is expected to be a record peak demand period.
The proposed change has been reviewed and it has been determined that there are no adverse safety or environmental impacts associated with the proposed change.
This change is considered to be a Class III amendment pursuant to 10 CFR 170.22.
Therefore, a check in the amount of $4,000 is enclosed.
Ve.ry truly yourd h ' e lD. CU h William O. Parker, J k
GAC/jfw Attachment cc:
Mr. P. R. Bemis Mr. James P. O'Reilly, Regional Administrator Senior Resident Inspector U. S. Nuclear Regulatory Commission McGuire Nuclear Station Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 0
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1 Mr. Harold R. Denton, Director Page 2 January 11, 1982 WILLIAM 0. PARKER, JR., being duly sworn, states that he is Vice President of Duke Power Company; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Commission this revision to the McGuire Nuclear Station Technical Specifications, Appendix A to License No. NPF-9; and that all statements and matters set forth therein are true and correct to the bes[of his know st'.
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1 N um (3 Li William 0.. Parker, Jr.( j e President i
Subscribed and sworn to before me this lith day of January, 1982.
_:-1 t r $Y tr Notary Public My Commission Expires:
September 20, 1984 l
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i McGuire Nuclear Station Technical Specification 3/4.5.4 - Baron Injection System Proposed Change Revise 3. 5.4.1 b. to read:
"b. Between 2000 and 22,500 ppm of boron, and" I
Justification and Safety Analysis The design function of the Boron Injection Tank (BlT) is to provide concentrated boric acid to the reactor coolant in order to minimize the impact of the reactivity addition resulting from a steam line break accident and the existance of a negative moderator coefficient of reactivity. The core moderator temperature coefficient of reactivity is most negative at core end-of-life, and from the standpoint of core reactivity the accident is most limiting at end-of-life conditions. The existing safety analysis of the steam line break accident is based on a conservatively assumed end-of-life moderator temperature coefficient of -41 PCM/ F, minimum shut-down margin (1.6%), and a BIT boric acid concentration of 20,000 PCM.
McGuire Unit I is currently in beginning-of-cycle 1 operation and has core burnup of approximately 20 EFPD. The moderator coefficient is approximately -10 PCM/ F.
Furthermore, the available core shutdown margin at this time of core operation has a significant margin compared to the value assumed in the safety analysis (3.27%
i versus 1.6%).
With these core parameters, the reactivity transient resulting from a postulated steam line break would be of very little severity compared to the worst case conditions assumed in the safety analysis and that the functioning ECCS with the normal RWST boron concentration of 2000 ppm would adequately mitigate the event.
Furthermore, a recent re-analysis of the steam line break accident for end-of-life conditions without considering the functioning of the BIT showed that the accident is safely mitigated.
A cursory review of this re-analysis was performed by the NRC resident inspectors Paul Barnett and Paul Bemis.
The foregoing assessment demonstrates that the proposed Technical Specification change reducing the BIT concentration from 20,000 ppm to 2000 ppm does not unduly compromise the safety of plant operation or the health and safety of the public.
Additionally, considering the probability of a steam line break, full power operation with a reduced BIT concentration for a period of one week is acceptable.
8201250294 820111 PDR ADOCK 05000369 P
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