ML20098E795

Application for Amend to License DPR-16,consisting of Tech Spec Change Request 130,revising Acceptance Criteria for Combined Leakage Rate of Penetrations & Isolation Valves Subj to Types B & C Testing

ML20098E795
Person / Time
Site:	Oyster Creek
Issue date:	09/25/1984
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20098E787	List: ML20098E786 ML20098E795 ML20098E798
References
NUDOCS 8410010387
Download: ML20098E795 (7)

Text

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S GPU NUCLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE NO. DPR-16 TECHNICAL SPECIFICATION CHANGE REQUEST N0.130 DOCKET NO. 50-219 Applicant submits by this Technical Specification Change Request No.130 to the Oyster Creek Nuclear Generating Station Technical Specifications, changes

- to Section 4.5.F.1.b.

h By (f/ V L PeterMiedler Vice President and Director Oyster Creek Sworn and subscribed to before me thisdE day of T m D r1984.

k kf4 d6SN4 N A Notary Public of NJ JANICE L BONDEMORE NOTARY PUBUC 0F NEW JERSEY g w Empim My 3L 1W5

8410010387 840925 PDR ADOCK 05000219 P PDR

..7 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION s- ,

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.130 for the Oyster Creek Nuclear Generating Station Technical Specifications, filed with the United States Nuclear Regulatory Commission on- September 25, 1984, has this day of September 25, 1984, been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:

The Honorable Henry A. Delo, Jr.

Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 P

By W  ;

Peter B.-Tiedler Vice President and Director Oyster Creek DATED: September 25, 1984 PBF: dam

d . v-GPU Nuclear Corporation NggIg7 Post Office Box 388 Route 9 South l Forked River,New Jersey 08731-0388 l

609 971-4000 Writer's Direct Dial Number:

~

September 25, 1984 The Honorable Henry A. Delo, Jr.

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

Dear Mayor Delo:

Enclosed herewith is one copy-of the Technical Specification Change Request No.130 for the Oyster Creek Nuclear Generating Station Operating License.

This document was filed with the United States Nuclear Regulatory Commission on September 25 , 1984.

Very truly yours, et Fiedler Vice President and Director Oyster Creek PBF: dam Enclosure l

GPU Nuclear Corpporation is a subsidiary of the General Pubhc Utihties Corporation

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OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE N0. DPR-16 L DOCKET N0. 50-219 E TECHNICAL SPECIFICATION CHANGL .(EQUEST NO. 130 y R

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

1. Section to be changed: F 4.5.F.1.b

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2. Extent of change:

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Remove the percentage requirements for specific Type B and C tests and =

replace with an overall combined Type B and C acceptance criteria.

[-

3.. Discussion:

h On August 7,1975, the NRC requested Jersey Central Power and Light (JCP&L) to review the containment leakage testing program for the Oyster Creek Nuclear Generating Station and to provide a plan for achieving full

-)

E 1 compliance with the requirements of 10 CFR 50, Appendix J.  ;

By JCP&L letter dated December 24, 1975, as supplemented by letters dated 7 August 12, 1976, November 22, 1978 and June 27, 1980, JCP&L submitted -

their proposed plans for meeting the Appendix J criteria. On March 4, 7 1982, the NRC issued the Safety Evaluation for the Appendix J review, r finding the analysis submitted by JCP&L to be acceptable.

{

The next step was for JCP&L (now the responsibility of GPU Nuclear) to -

develop and submit the proposed Technical Specificatons. While this .

submittal is in the process of being written, there is a change that must "

be made now in order for Oyster Creek to successfully complete their -

Appendix J testing during this cycle 10 outage. =

The Oyster Creek Technical Specifications, Section 4.5.F.1.b specifies -

allowable limits for double gasketed seals, testable penetrations and isolation valves, and primary containment air purge penetrations and reactor building to torus vacuum relief valves. Together, these limits -

comprise the acceptance criteria for the combined leakage rate of all penetrations and isolation valves subject to Type B and C tests which must -

be less than 0.60 of the maximum allowable limit (La) adjusted to 20 psig. As a result of our commitment to Type C test additional isolation '

valves, it has become difficult to meet the 30% L t o(20) limitation for =

testable penetrations and isolation valves.

In reviewing Specification 4.5.F.1.b, it has been determined that acceptance should not be based on the individual leakage of the various j{

types of penetrations and valves, but should be based on the combined leakage of all penetrations and valves which are required to be Type B and 4 A

C tested.

.=

. GPU Nuclear is making an effort to reviss the Oyster Creek Technical r

Specifications to incorporate the Appendix J requirements. This effort is nearing completion but, it is important that we now submit this advance change to bring the acceptance criteria for the combined leakage rate of all penetrations and valve subject to Type B and C tests up-to-date.

This proposed change request is consistent with the intent for meeting tne 10 CFR 50, Appendix J requirements as outlined in our submittals, the NRC safety evaluation of these submittals, and the acceptance criteria as stated In'10 CFR 50, Appendix J, Section III.C.3.

OYSTER CREEK NUCLEAR GENERATING STATION

' PROVISIONAL OPERATING LICENSE NO. DPR-16

. DOCKET NO. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 130 i-Pursuant to 10 CFR 50.91, an analysis concerning significant hazards

. considerations is provided below:

t

.l. Section to be changed:-

4.5.F.1.b

2. - Extent of change:

- Remove the percentage requirements for specific Type B and C tests and replace with an overall combined Type 8 and C acceptance criteria.

3. Discussion:

~

- 0n August 7,1975, the NRC requested Jersey Central Power and Light 4

- (JCP&L) to review the containment leakage testing program for the Oyster Creek Nuclear Generating Station and to provide a plan for achieving full compliance with the requirements of 10 CFR 50, Appendix J.

By-JCP&L letter. dated December 24, 1975, as supplemented by letters dated August 12,.1976, November 22, 1978 and June 27, 1980, JCP&L submitted their-proposed plans for meeting the Appendix J criteria. On March 4, 1982, the NRC. issued the Safety Evaluation- for the Appendix J review, ,

finding the analysis submitted by JCP&L to be acceptable.

The next step was for JCP&L (now the responsibility of GPU Nuclear) to develop and submit the proposed Technical -Specificatons. Wnile this submittal is in the process of being written, there is a change that must

be made now in order for Oyster Creek to successfully complete their

- Appendix J testing during this cycle 10 outage. .

l The Oyster Creek Technical Specifications, Section 4.5.F.1.b specifies

( allowable limits for double'gasketed seals, testable penetratfons and isolation valves, and primary containment air purge penetrations and reactor building to torus vacuum relief valves. Together, these limits comprise the acceptance criteria for the comnined leakage rate of all penetrations and isolation valves subject to Type B and C tests which must

- be less than 0.60 of the maximum allowable limit (La) adjusted to 20 psig. As a result of our comitment to Type C test additional isolation valves, it has become-difficult to meet the 30% tL o(20) limitation for testable penetrations and isolation valves.

In reviewing Specification 4.6.F.1.b, it has been determined that acceptance should not be based on the individual leakage of the various ,

types of penetrations and valves, but should be based on the combined

- leakage of all penetrations and valves which are required to be Type B and C tested.

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i GPU Nuclear is ' making an effort to revise the Oyster Creek Technical Specifications to incorporate the Appendix J requirements. This effort is I

nearing completion but, it is important that we now submit this advance change to bring the acceptance criteria for the combined leakage rate of all penetrations and valve subject to Type B and C tests up-to-date.

This proposed change request is consistent with the intent for meeting the 10 CFR 50, Appendix J requirements as outlined in our submittals, the NRC safety evaluation of these submittals, and the acceptance criteria as stated in 10 CFR 50, Appendix J, Section III.C.3.

We have . determined that this change request involves no signifcant 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 consequences of -

an accident previously evaluated; or 3 l

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.

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