ML20056H306
| ML20056H306 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/30/1993 |
| From: | Hagan J Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20056H307 | List: |
| References | |
| LCR-93-11, NLR-N93140, NUDOCS 9309090134 | |
| Download: ML20056H306 (7) | |
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Eectne and Gas Company Joseph J. Hagan Pubhc Service Electnc and Gas Company P.o. Box 236. Hancocks Bndge. NJ 08038 609-339-1200 va rmem rwo,ar opmio%
AUG 3 01993 NLR-N93140 t
LCR 93-11 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 j
Gentlemen:
LICENSE AMENDMENT APPLICATION FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 This letter submits an application for amendment to Appendix A of Facility Operating License NPF-57 for the Hope Creek Generating i
Station, and is being filed in accordance with 10CFR50.90.
The j
amendment request would revise the composition of the Station Operations Review Committee (SORC) and increase the submittal interval of the Radiological Effluent Release Report from semiannually to annually.
I A description of the requested amendment, supporting information-and analyses for the change, and the basis for a no significant i
hazards consideration determination are provided in Attachment 1.
l The Technical Specification pages affected by the proposed change are marked-up in Attachment 2.
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Pursuant to the requirements of 10CFR50.91(b) (1), a copy of this I
request for amendment has been sent to the State of New Jersey.
I Upon NRC approval of this proposed change, PSE&G requests that the amendment be made effective on the date of issuance, but l
implemented within 60 days to provide sufficient time for associated administrative activities.
Should you have any questions regarding this request, we will be pleased to discuss them with you.
Sincer ly,
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l 080048 9309090134 930830 iS DR ADOCK 05000354 N
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AUG 3 01933 Document Control Desk NLR-N93140 Affidavit Attachments (2)
C Mr. T. T. Martin, Administrator - Region I U.
S.
Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr.
S.
Dembek, Licensing Project Manager U.
S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr.
S.
T. Barr (SO9)
USNRC Acting Senior Resident Inspector Mr.
K.
Tosch, Manager IV i
NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 i
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REF: NLR-N93140 LCR 93-11 STATE OF NEW JERSEY
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COUNTY OF SALTA
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J. J.
Hagan, being duly sworn according to law deposes and says:
I am Vice President - Nuclear Operations of Public Service f
r Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning the Hope Creek Generating Station, are true to the best of my knowledge, information and belief.
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Subscribed and Sworn to before me this CM dayof6/1(nAIs 1993
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Notary Public of New Jersey l
KIMBERLY JO BROWN l
NOTARY FUBLIC OF My Commission expires on W cem:,,;,,, r.,:... NEW JfRSEY
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A'ITACHMENT 1 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS LICENSE AMENDMENT APPLICATION FACILITY OPERATING LICENSE NPF-57 NLR-N9314 0 HOPE CREEK GENERATING STATION LCR 93-11 DOCKET NO. 50-354 I.
DESCRIPTION OF THE PROPOSED CHANGES As indicated on the marked-up pages in Attachment 2, PSE&G requests that:
1)
Technical Specification 6.5.1.2 be revised such that the Radiation Protection / Chemistry Manager position is eliminated, the Radiation Protection Engineer title is changed to Radiation Protection Manager, and the Chemistry Engineer title is changed to Chemistry Manager.
Both the Radiation Protection Manager and the Chemistry Manager will be Station Operations Review Committee (SORC) members.
2)
Technical Specification 6.9.1.7 be revised to increase the submittal interval of the Radiological Effluent Release Report (RERR) from semiannually to annually in accordance with 10CFR50. 3 6a (a) (2).
In addition, Specifications 3.3.7.10, 3.3.7.11, 3.11.1.4, 3.12.1, 3.12.2, 6.13.2, 6.14.2, Table 3.12.1-1 Note 1, Table 4.11.1.1.1-1 Note c, and Table 4.11.2.1.2-1 Note b will be revised to reflect this change by eliminating references to the Semiannual RERR.
II.
REASON FOR THE CHANCES The proposed changes to Specification 6.5.1.2 make the Technical Specifications consistent with the functional position titles currently used at Hope Creek.
The proposed change to the submittal interval of the RERR from semiannually to annually makes the Technical Specifications consistent with the requirements of 10CFR50.36a(a) (2).
The proposed changes to Specifications 3.3.7.10, 3.3.7.11, 3.11.1.4,
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3.12.1, 3.12.2, 6.13.2, 6.14.2, Table 3.12.1-1 Note 1, Table 4.11.1.1.1-1 Note c, and Table 4.11.2.1.2-1 Note b delete the term " Semiannual" in the references to the RERR of Specification 6.9.1.7 in order to make the Technical Specifications consistent.
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LCR 93-11 Administrative Controls changes NLR-N93140 i
III.
JUSTIFICATION FOR THE CHANGE The changes to Specification 6.5.1.2 are being made in order to reflect personnel changes that have taken place at Hope Creek.
The position of Radiation Protection / Chemistry Manager was eliminated and its functions replaced by the positions of Radiation Protection Manager and Chemistry Manager.
Both the Radiation Protection Manager and the Chemistry Manager will satisfy the same SORC membership requirements established previously for the Radiation Protection Engineer and Chemistry Engineer.
The proposed change in the submittal interval of the Radiological Effluent Release Report from semiannually to annually is being made in accordance with 10CFR50.36a.
10CFR50.36a was recently revised as part of the NRC's reduction of the regulatory burden on utilities.
IV.
Sionificant Hazards Consideration Evaluation PSE&G has, pursuant to 10CFR50.92, reviewed the proposed amendment to determine whether our request involves a significant hazards consideration.
We have determined that operation of the Hope Creek Generating Station in accordance with the proposed changes:
1.
Will not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed amendment to eliminate the Radiation Protection / Chemistry Manager position and establish the Radiation Protection Manager and Chemistry Manager as Station Operations Review Committee (SORC) members, as well as the proposed change to the RERR submittal frequency from semiannually to annually are changes that are administrative in nature.
Therefore, the above changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
2.
Will not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed amendment does not involve any physical changes to plant structures, systems or components, or change the manner in which the plant is operated.
Therefore, the proposed changes will not increase the probability of accidents of a different type, nor will they create malfunctions of a different type than any previously evaluated in the SAR.
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l LCR 93-11 Administrative Controls Changes NLR-N93140 i
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Will not involve a significant reduction in a margin of safety.
The basis for this statement is outlined in Item I above.
V.
Conclusion i
Based on the preceding discussion, pSE&G has concluded that the proposed change to the Technical Specifications does not involve a significant hazards consideration insofar as the change:
(i) does not involve a significant increase in the probability or consequences of an accident previously evaluated, (ii) does not create the possibility of a new or different kind of accident I
from any accident previously evaluated, and (iii) does not involve a significant reduction in the margin of safety.
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ATTACHMENT 2 LICENSE AMENDMENT APPLICATION, LCR 93-11, NLR-N93140 FACILITY OPERATING LICENSE NPF-57 l
HOPE CREEE GENERATING STATION DOCKET NO. 50-354 I
TECHNICAL SPECIFICATION PAGES WITH PEN AND INK CHANGES The following Technical Specifications for Facility Operating License No. NPF-57 are affected by this license amendment request:
Technical Specification P_aaes 6.5.1.2 6-7 3.3.7.10 3/4 3-91 3.3.7.11 3/4 3-96 Table 4.11.1.1.1-1 3/4 11-4 P
3.11.1.4 3/4 11-7 Table 4.11.2.1.2-1 3/4 11-11 3.12.1 3/4 12-2 Table 3.12.1-1 3/4 12
't 3.12.2 3/4 12-13 6.9.1.7 6-19, 6-20 6.13.2 6-24 6.14.2 6-24 INDEX xxvi l
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