ML20086H687
| ML20086H687 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 11/29/1991 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20086H689 | List: |
| References | |
| LCR-91-09, LCR-91-9, NLR-N91156, NUDOCS 9112090295 | |
| Download: ML20086H687 (8) | |
Text
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Pubhc Lorvice Uectric and Gas Confony Stanley LaDruna Pubhc Service (!ectnc and Gas Company P 0. Box 236. Hancocks Dndge, NJ 08038 (,09 339,1200 vu v.ewa aun a:ww.,s N OV I' ) 1991 NLR-N91156 LCR 91-09 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
LICENSE AMENDMENT APPLICATION ONE TIME EXTENSION OF CONTAINMENT LEAK RATE TEST INTERVAL FACILITY OPERATING LICENSE NPF-57
!! OPE CREEK GENERATING STATION DOCKET NO. 50-354 Public Service Electric and Gas Company (PSE&G) hereby submits a request for amendment of Facility Operating License NPF-57 for the Hope Creek Generating Station in accordance with 10 CFR 50.90.
A copy of this submittal has been sent to the state of New Jersey as indicated below pursuant to the requirements of 10 CFR 50.91(b) (1).
The proposed change would permit a one-time extension of the Type A overall Integrated Containment Leak Rate Test interval.
Additionally, the change would delete a note which allowed a one-time-extension of the Type B and C test intervals to the first refueling outage and is no longer applicable.
PSE&G believes that this submittal contains sufficient technical justification to conclude tnat a detailed specialist review should not-be required and that the proposed change can be classified as a Category 2 change. includes a description, justification and significant hazards analysis for the proposed change.
Attachment
'2 contains marked up Technical Specification pages which reflect i
.the proposed change.
Upon NRC approval, please issue a License Amendment which will be effective upon issuance and shall be implemented within 60 days of issuance.
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Document Control Desk 2
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"' '3 NLR-N91156 Should you have any questions or comments on this submittal, please do not hesitat.o to contact us.
Sincerely,
,9 a: /2 J'lp)icil?A&Y'i<c s s
Affidavit Attachments (2)
C Mr.
S.
Dembek Licensing Project Marmger Mr.
T.
Johnson Senior Resident Inspector Mr.
W.
T.
Russell Administrator - Region 'l Mr. Kent Tosch, Chief -New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415
+
Trenton, NJ 08625
Ref:
NLR-N 91156 LCR 91-09
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STATE OF NEW JERSEY
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Ss.
COUNTY OF SALEM
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S.
LaBruna, being duly sworn according to law deposes and says:
I am Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, 1 find the matters set forth on our Jetter dated 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 c2 7 day of h h fo), 1991 Atk/fft O. dza Notary Ehlblic o[/ Nek Jersey ELIZADETri J. K1DD Nota *y P2hc of New Jersey My Commission expires on My Comhim Ewn Amd E PAS w
ATTACHMENT 1 REQUEST FOR LICENSE AMENDMENT ONE-TIME EXTENSION OP CONTAINMENT LEAK RATE TEST INTERVAL FACILITY OPERATING LICENSE iiPF-57 IlOPE CREEK GENERATING STATION DOCKET NO. 50-354 h
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HOPE CREEK LCR 91-09 HLR-N91156 I.
Description of the Prgoosed Channes
.This amendment request proposes that Technical Specification 4.6.1.2.a be revised to allow a one time interval of 53 months for the _ Type A Ccintainment Integrated Leak Rate Test (ILRT).
The present interval is 40 10 months.
Additionally, it is requested to delete the note pertaining Po Technical Specification 4.6.1.2.d.
This note allowed a one-time extension of the Type C test interval, for specific valves, to the first refueling outage.
II.
Reason [gr the Proposed Chances Hone Creek Technical Specification 4 6.3.2.a This Technical Specification (TS) specifies that three Type A Overall Integrated Containment Leakage Rate testa (ILRT) shall be conducted at 40 1 10 month intervals during each 10-year service period; the third test of each set shall be conducted during the shutdown for the ten-year plant inservice inspection.
Additionally, 10 CFR 50, Appendix 7,Section III..D.1.(a). states that the set of three Type A tests shall be performed "... at a? proximately _ equal intervals during each 10-year service period."
- The first-operational Type A ILRT of the Hope Creek containment was successfully completed during the second refuel outage in November 1989.
Incofar as the third test must be completed during the 10-year in-service inspection outage schedule 6 for March'through May 1997, an option exists as to wnether to perform the second test during the fourth or during the fifth re::cel
-outage.
Completion of the second ILRT during the fourth refuel outage, scheduled for September through November 1992, would result in an interval of 34-36 months between the.irst and second tests, thus fulfilling the TS limit of 40 10 months.
However, this would also result in an interval of 54-56 months.between the second and third tests exceeding the TS limit by 4 to 6 months.
Completion of the second ILRT during the fifth refuel outage, schede'_ed for March through April 1994, would result in intervals of 52-53 months between the first and second tests and 35-38 montha between the second and third tests.
In this case the second test interval would exceed the TS limit by 2 or 3 months.
PAGE 1 OF 4 l
ATTACHMENT 1
HOPE CREEK LCR 91-09 l
l NLR-N91156 Upon consideration of the two preceding alternatives, PSE&G has determined that it would be.aore prudent to schedule performance of the second IIRT during the fifth refuel outage for the following reasons:
1.
Although an extension of the TS test interval is required for either option, the duration of the ex';cnsion is less (ie. 3 months as opposed to 6 months).
2.
The second and third test intervals will be more evenly distributed (52-53 and 35-28 months as opposed to 34-36 and 54-56 months).
Therefore, this change is being requested to provide a one tira extension of the TS test interval lirit from 40 1 10 months to 53 months to allow the second ILRT to be performed during the fif th rcfuel outage.
11 ope _ Creek Teclu)ical Snecification 4.6.1.2.d The note pertaining to this TS allowed a one-time extension of the Type C test interval to the first refueling outage.
This extension applied to specific prJmary containment isolation valves that had been identified in PSE&G's letter to the NRC (letter No. N LR-N87 047 ) dated Aptil 3, 1987.
Insofar as the first refueling ot tage has been corapleted, the note is no longer applicable and should be removnd from Technical Specifications to improve clarity, III. Just'ificAtlon for the Proposed Channes Hope Creek Teshnical Snecificatiore 4.6.1.2.a The intent of the established testing intervals is to conduct three tests at approximately equal intervals within a given ten year period with the third test coinciding with the ten year in-service inspection outage.
The first Type A test was completed successfully during the second refuel outage in November 1989.
Since then, there has not been any modifications made to the plant which could adversely offect the test results.
Type B and C tests have been completed satisfactorily during each of the three previous Hope Creek outages and is scheduled to be performed during the upcoming fourth refuel outage.
Demonstrated operability of'the associated components and penetrations provides additional assurance that the integrated containment leak rate remains satisfactory.
PAGE 2 OF 4 ATTACHMENT 1
HOPE CREEK LCR 91-09 NLR-N91156 Additionally, it should be noted that the most race.' Proposed Rule, Appendix-J to 10 CFR 50 (April 8, 1991), Sectics.
II.A.3.c-allows a single Type A' test interval to be extended for up to 25V
.of the specified four year interval (ie, pp to 60 months).
The proposed changc to TS 4.6.1.2.a to the fifth refueling outage would remain within the test frequency allowed in the proposed rule.
This-in a one-time Type A test interval extension request.
A new Type A test schedule will be proplanned for the next ten year service period.
Hone Creek Technical Specification 4.6.1.2.d
'1co note pertaining to this TS -is no longer applicable and will not.be applicable in the future.
Therefore, deletion of the note is purely administrative in nature and should require no further justification.
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PAGE OF 4 l
ATTACHMENT 1
l HOPE CREEK LCR 91-09 l
NLR-N91156 IV.
Significant 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.
Fe 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.
AlthorJh the propose! change extends the 40 i 10 month test interval by 3 months, first Type A test was completed successfully.
Since then, there has not been any modifications made to the plant which could adversely effect the test results.
Type B and C tests have been completed satisfactorily during each of the three prezious Hope Creek outages and is scheduled to be performed during the upcoming fourth refuel outage.
Demonstrated operability of the associated components and penetrations provides additional assurance that the integrated containment leak rate remains satisfactory.
2.
Will not create the possibility of a new or different kind of accident from any accident previously evaluated.
The propased change does not adversely effect the design or operation of any system or component important to safety.
No physical plant modifications or new operational configurations will result from this change.
3.
Will not involve a significant reduction in a margin of safety.
The fir.c Type A test was completed satisfactorily.
Type B and C tests have been completed satisfactorily and will be performed during the fourth refuel outage.
No plant modifications have been made which could adversely effect Type A test results.
V.
Conclusion Based on the preceding discussion, PSE&G has concluded that the proposed change to the Technical Specifications does not involve 3
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 from any accident previously evaluated, and (iii) does not involve a significant reduction in a margin of safety.
PAGE 4 OF 4 ATTACHMENT 1 l
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