ML20056G944
| ML20056G944 | |
| 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 | |
| ML20056G945 | List: |
| References | |
| LCR-93-20, NLR-N93141, NUDOCS 9309070351 | |
| Download: ML20056G944 (6) | |
Text
i Pubhc Semm i
Dectnc and Gas Company t
Joseph J. Hagan Public Sennce Dectnc and Gas Company P.O. Box 236 Hancocks Bndge, NJ 08038 609-339-1200 v.ce e,eante o - Nociem comano a AUG 3 01993 NLR-N93141 LCR 93-20 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
LICENSE AMENDMENT APPLICATION FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION DOCITT NO. 50-354 This letter submits an application for amendment to Appendix A of Facility Operating License NPF-57 for the Hope Creek Generating Station, and is being filed in accordance with 10CFR50.90.
The amendment request would revise sections 3.11.2.7 and 3.8.4.1 of the. Hope Creek Generating Station Technical Specifications.
A description of the requested amendment, supporting information and analyses for the change, and the basis for a no significant hazards consideration determination are provided in Attachment 1.
The Technical Specification pages affected by the proposed change are marked-up in Attachment 2.
Pursuant to the requirements of 10CFR50.91(b) (1), a copy of this request for amendment has been sent to the State of New Jersey.
Upon NRC approval of this proposed change, PSE&G requests that l
the amendment be made effective on the date of issuance, but implemented within 60 days to provide sufficiant time for associated administrative activities, j
Should you have any questions regarding this request, we will be pleased to discuss them with you.
Sincerely, l
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AUG 3 01993 Document Control Desk "
NLR-N93141 l
Attachments (2)
C Mr. T.
T. Martin, Administrator - Region I U.
S.
Nuclear Regulatory Commission 475 Allendale Road I
King of Prussia, PA 19406
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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 NJ Department-of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 i
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e REF: NLR-N93141 LCR 93-20 STATE OF NEW JERSEY
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COUNTY OF SALEM
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J.
J.
IIagan, being duly sworn according to law deposes and says:
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I I am Vice President - Nuclear Operations of Public Service
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Electric and Gas Company, and as such, I find the matters set l
forth in the above referenced letter, concerning the llope Creek Generating Station, are true tc the best of my knowledge, information and belief.
i Subscribed and Sworn to before me
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this d OT day of,f _/ u f M. f a f
1993 n XA /
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Notary Public of New Jersey KIMBEllLY JO BROWN d
NOTARY PUBilC Of NEWJERSEY My Commission expires on
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ATTACHMENT 1 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS LICENSE AMENDMENT APPLICATION FACILITY ""ERATING LICENSE NPF-57 NLR-N93141 HOPE CREE GENERATING STATION LCR 93-20 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)
Table 3.8.4.1-1 be revised to delete Breaker No.
52-263022.
This breaker was disconnected and converted to spare status by a plant design change.
2)
Technical Specification 3.11.2.7 be revised such that
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the radioactivity rate units are in microcuries/sec instead l'
of millicuries /sec, the action statement reference to HOT STANDBY is changed to HOT SHUTDOWN, and the reference to the Offgas Radioactivity Monitor (in Surveillance Requirement 4.11.2.7.2.b) is changed to Offgas Pretreatment Radiation Monitor.
II.
HEbSON FOR THE CHANGES Breaker No. 52-263022 was disconnected and converted to " spare" status by a plant design change.
However, the requirement to tag this breaker open stil] exists in station operating procedure HC.OP-IO.ZZ-0002.
The procedural requirement cannot be deleted until this Technical Specification is revised.
Specification 3.11.2.7 is being changed to make the units of radioactivity rate consistent with the station chemistry reports, the station RMS data, and other Technical Specifications.
The change from HOT STANDBY (a mode switch position) to HOT SHUTDOWN i
(an operational condition) is an editorial correction that makes i
the action statement for 3.11.2.7 consistent with the other Technical Specifications.
In addition, the change from Offgas Radioactivity Monitor to Offgas Pretreatment Radiation Monitor in Surveillance Requirement 4.11.2.7.2(b) is an editorial correction that more clearly specifies the subject monitor.
Page 1 of 3 l
LCR 93-20 Specification 3.8.4.1 and 3.11.2.7 Changes NLR-N93141
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III.
JUSTIFICATION FOR THE CHANGE l
Breaker No. 52-263022 was disconnected and converted to " spare"
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status by a plant design change, therefore the requirements of Specification 3.8.4.1 no longer apply to this breaker.
The changes for Specification 3.11.2.7 make the units of the radioactivity rate of noble gases consistent with the station chemistry reports, plant RMS data and other Technical Specifications.
The Technical Specification limit for the radioactivity rate will not change, for the 330 millicuries /sec rate is converted to an equal rate of 3.30 E+5 microcuries/sec.
The change from HOT STANDBY to HOT SHUTDOWN is an editorial correction that makes the action statement fo*
2.7 consistent with the other Technical Specificatic Furthermore, the change in the Offgas Radioactivity Monitor reference to Offgn2 Pretreatment Radiation Monitor is an editorial one that more accurately specifies the subject monitor.
t IV.
Sionificant Hazards Consideration Evaluation PSE&G has, pursuant to 10 CFR 50.92, 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 change to Table 3.8.4.1-1 would delete Breaker No. 52-263022.
This change is administrative in nature and would in no way affect the znitial conditions, assumptions, i
or conclusions of the Hope Creek accident analyses.
Likewise, the proposed changes to Specification 3.11.2.7 which replace " millicuries" with "microcuries," " HOT STANDBY" with " HOT SHUTDOWN," and "Offgas Radioactivity Monitor" with "Offgas Pretreatment Radiation Monitor," are administrative in nature and do not affect the initial conditions, assumptions, or conclusions of the Hope Creek i
accident analyscs.
These changes do not affect the i
operation or performance of any equipment assumed in the accident analyses.
Therefore, based on the above information, we conclude that the proposed changes would not significantly increase the probability or consequences of any accident previously evaluated.
i Page 2 of 3
l ATTACHMENT 2 i
LICENSE AMENDMENT APPLICATION, LCR 93-20, NLR-N93141 FACILITY OPERATING LICENSE NPF-57 IlOPE CREEK GENERATING STATION DOCKET NO. 50-354 l
TECHNICAL SPg.Cllh 'STL(L!i_PAGES WITH PEN AND INK CHANGES i
The follce "dchnical Specifications for
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Facility,
i.ng License No. NPF-57 are affected by.this~~
mendment request:
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Attach 8ent 1 LCR 93-20 Specification 3.8.4.1 and 3.11.2.7 Changes NLR-N93141 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 j
evaluated in the SAR.
l 3.
Will not involve a significant reduction in a margin of safety.
I The basis for this statement is outlined in Item I above.
V.
Conclusion 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:
(1) 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 from any accident previously evaluated, and (iii) does not involve a significant reduction in the margin of safety.
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