ML20093M990

Application for Amend to License DPR-16,consisting of Rev 1 to Tech Spec Change Request 69,submitting Radiological Effluent & Ets,Revising Sections 3.6.A & 4.6.A & Incorporating Reporting Requirements in Generic Ltr 83-43

ML20093M990
Person / Time
Site:	Oyster Creek
Issue date:	10/22/1984
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20093M986	List: ML20093M984 ML20093M990 ML20093M998
References
GL-83-43, NUDOCS 8410310194
Download: ML20093M990 (5)

Text

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0YSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE NO. DPR-16 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 69. REVISION 1 DOCKET NO 50-219 Applicant submits by this Technical Specification Change Request No. 69, Revision 1, to the Oyster Creek Nuclear Generating Station Technical Specifications, the Radiological Effluents Technical Specifications.

By:

Peter 8. Fiedler Vice President and Director Oyster Creek Sworn to and subscribed to before me this 44 day ofbtAs ,1984, ddhldiD Notary Public of New Jersey A No ry P b c of er.cy My Coensisehm hpises June 9,19ths 3

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L UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF )

) DOCKET NO. 50-219 GPU NUCLEAR CORPORATION )

CERTIFICATE OF SERVICE This is to certify that a copy of Technical Specification Change Request No. 69, Revision 1, for the Oyster Creek Nuclear Generating Station Technical Specifications filed with the United States Nuclear Regulatory Conais2 ion on October 22 ,1984, has this day of October 22 , 1984, been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:

Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 By: - -

o Peer u.1 .edler Vice President and Director Oyster Creek DATED: October 22, 1984 PBF: dam l

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. s. . ;4 OPU Nuclear Corporation e N ' 'T b Route ou h Forked River,New Jersey 087310388 609 971 4000 Writer's Direct Dial Number:

October 22, 1984 Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731

Dear Mayor:

Enclosed is one copy of Technical Specification Change Request No. 69, Revision 1 for the Oyster Creek Nuclear Generating Station Operating License.

This document was filed with the United States Nuclear Regulatory Comrnission on October 22, 1984.

Very truly yours,

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Vice President and Director Oyster Creek PBF/ dam 0764A Enclosure i

GPU Nuclear Corporation is a subs @ary of the General Pubhc Utihties Corporation

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OYSTER' CREEK NUCLEAR GENERATING STATION

+[ PROVISIONAL OPERATING LICENSE NO. DPR-16 J00CKET NO. 50-219

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TECHN,ICAL SPECIFICATION CHANGE REQUEST NO. 69 Revision 1 z .

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Applicant hereby requests the Commission to change Appendix A to the above captioned license as follows:

1. Sections +to be changed:

Table of Contents, 1.19, 1.30 through F.36, Table 3.1.1, sections:

3.6, 3.14, 3.15, table 4.1.1, table 4.1.2, sections: 4.6, 4.14, 4.15,

.,_ ) 4.16,'6.5.3, 6.6, 6.8, 6.9, 6.10, 6.17, 6.18 and 6.19.

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2. Extent of changes: '

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To incorpo'r ate the requircaients' of 10 CFR 50 Appendix I,

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3. Discussion: -

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i 9 On June I.,[1979, Jersey Central Power and Light Company (JCPaL)

\ submitted Tichnical Specification Chinge Request No. 69 to incorporate

' the requirements of 10 CFR 20,10 CFR 50.34a,10 CFR 50.36a, 10 CFR 50,'and 40 CFR 150,: This submittal was discussed in a meeting with the NRC staff on Septemoer 13, 1979 and it was agreed that revisions were, required. B,

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• e u By letter dated February 15, 1980,- JCPal submitted Technical Specification CNnge Request No. 79 which incorporated the 10 CFR 50 Appencilx i design objectives for gaseous effluent releases. This submittal,was issued as Amendment 49 to the Oyster Creek Technical

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Specifications and was designed to De a temporary change, to be replaced after the complete Radiological Effluent Technical

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.Offgas Specifications Systim. (RETS( (are issued for Oyster Creek and the Augment

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On February 3-4, 052,.the NRC met with GPU Nuclear to discuss tne Oyster Creek RETS 'subalittal. This meeting resulted in additional NRC questions which were' resp ~onsed to by GPUN letters dated March 30, 1982 and August 20,1982.y

' 4' The attached proposed RETS is a cumulation of the discussions and submittals Detween the NRC and GPUN over the last few years. This

". suomittal meets the intent of 10 CFR 50 Appendix I,10 CFR 50.34A and 10 CFR 50.36a. > '

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0YSTER CREEK NUCLEAR GENERATING STATION

6 PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST N0. 69 Revision 1 Pursuant to 10 CFR 50.91, an analysis concerning significant hazards considerations is provided below:

1. Sections to be chan2ed_:

Table of Contents, 1.19, 1.30 through 1.36. Table 3.1.1, sections:

3.6, 3.14, 3.15, table 4.1.1, table 4.1.2, sections: 4.6, 4.14, 4.15, 4.16, 6.5.3, 6.6, 6.8, 6.9, 6.10, 6.17, 6.18 and 6.19,

2. Extent of changes:

To incorporate the requirements of 10 CFR 50 Appendix I.

3. Discussion:

On June 1,1979, Jersey Central Power and Light Company (JCPaL) submitted Technical Specification Change Request No. '69 to incorporate the requirements of 10 CFR 20, 10 CFR 50.34a, 10 CFR 50.364, 10 CFR 50, and 40 CFR 190. This suomittal was discussed in a meeting with the NRC staff on September 13, 1979 and it was agreed that revisions were required.

By letter dated February 15, 1980, JCPal submitted Technical Specification Change Request No. 79 wnicn incorporated tne 10 CFR 50 Appendix I . design oojectives for gaseous effluent reler.ses. Tnis submittal was issued as Amendment 49 to tne Oyster Crank Technical Specifications and was designed to be a temporary change, to be replaced after the complete Radiological Effluent Technical Specifications (RETS) are issued for Oyster Creek and the Augmented Offgas System.

On February 3-4, 1982, the NRC met with GPU Nuclear to discuss the Oyster Creek RETS submittal. This meeting resulted in additional NRC questions which were responsed to by GPUN letters dated Marcn 30, 1982 and August 20, 1982.

The attached proposed RETS is a cumulation of tne discussions and submittals between the NRC and GPUN over the last few years. This submittal raeets' the intent of 10 CFR 50 Appendix I,10 CFR 50.34A and 10 CFR 50.36a.

We have determined that this change request involves no significant hazards considerations in that operation of the Oyster Creek Plant in accordance with the proposed amendment will not:

1. Involve a significant increase in the probability or ccvequences of an accident previously evaluated; or

2. Create the probability of a new or different kind of accident from any accident previously evaluated; or

3. Involve a significant reduction in a margin of safety.