ML20066D373: Difference between revisions

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In accordance with the requirement of the Oyster Creek Technical Specifications GPU Nuclear submitted pressure-temperature (P-T) limits for operation beyond ten (10) effective full power years (EFPY) on January 19, 1988.
In accordance with the requirement of the Oyster Creek Technical Specifications GPU Nuclear submitted pressure-temperature (P-T) limits for operation beyond ten (10) effective full power years (EFPY) on January 19, 1988.
The P-T curves were developed based on the surveillance capsule results and on the draft Rev. 2 of Regulatory Guide (R.G.) 1.99. The curves were approved by the NRC staff and were issued on March 21, 1988 as Amendment No. 120 to Oyster Creek Technical Specifications. The current Oyster Creek Technical Specifications require that new P-T operating curves be developed for operation beyond 15 EPPY.
The P-T curves were developed based on the surveillance capsule results and on the draft Rev. 2 of Regulatory Guide (R.G.) 1.99. The curves were approved by the NRC staff and were issued on March 21, 1988 as Amendment No. 120 to Oyster Creek Technical Specifications. The current Oyster Creek Technical Specifications require that new P-T operating curves be developed for operation beyond 15 EPPY.
Subsequently, GPU Nuclear evaluated P-T limite using the calculational methods given in the final Rev. 2 of R.G. 1.99. The purpose of this evaluation was to identify the impact of the R.G. 1.99, Rev. 2 on the current P-T curves. The results of this evaluation was submitted by our letter dated July 26, 1989 in response to Generic Letter 88-11, "NRC Position on Radiation Embrittlement of Reactor Vessel Materials and its Impact on Plant Operations."
Subsequently, GPU Nuclear evaluated P-T limite using the calculational methods given in the final Rev. 2 of R.G. 1.99. The purpose of this evaluation was to identify the impact of the R.G. 1.99, Rev. 2 on the current P-T curves. The results of this evaluation was submitted by our {{letter dated|date=July 26, 1989|text=letter dated July 26, 1989}} in response to Generic Letter 88-11, "NRC Position on Radiation Embrittlement of Reactor Vessel Materials and its Impact on Plant Operations."
l The July 26, 1989 letter stated that another set of P-T operating curves for the Oyster Creek reactor vessel would be implemented by the end of 13R (May 1991). This plan complies with the schedule set forth in Generic Letter                                            j 88-11 which required licensees to update and fully implement new P-T curves
l The {{letter dated|date=July 26, 1989|text=July 26, 1989 letter}} stated that another set of P-T operating curves for the Oyster Creek reactor vessel would be implemented by the end of 13R (May 1991). This plan complies with the schedule set forth in Generic Letter                                            j 88-11 which required licensees to update and fully implement new P-T curves
                                                                                                                                 ]
                                                                                                                                 ]
within two (2) plant outages (approximately 3 years) after the effective date (May 1988) of Pevision 2 to Regulatory Guide 1.99, " Radiation Embrittlement of                                        l Reactor Vessel. Materials."                                                                                              l
within two (2) plant outages (approximately 3 years) after the effective date (May 1988) of Pevision 2 to Regulatory Guide 1.99, " Radiation Embrittlement of                                        l Reactor Vessel. Materials."                                                                                              l

Latest revision as of 16:29, 31 May 2023

Forwards Application for Amend to App a of License DPR-16, Consisting of Tech Spec Change Request 194,proposing New pressure-temp Limits Up to 17 EFPY & New Min Boltup Temp for Vessel Closure Head Stud Tensioning
ML20066D373
Person / Time
Site: Oyster Creek
Issue date: 01/11/1991
From: J. J. Barton
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20066D374 List:
References
RTR-REGGD-01.099, RTR-REGGD-1.099 C321-91-2006, NUDOCS 9101150015
Download: ML20066D373 (4)


Text

.s-4 9

GPU Nuclear Corporation 0 1 Nuclear =tr >"

Forked River, New Jersey 087310388 609 971-4000 Writer's Direct Dial Number:

Januarv 11, 1991 C321-91-2006

-U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:

Subjects Oyster Creek Nuclear Generating Station (OCNGS)

Docket No. 50-219 Technical Specification Change Request No. 194 In accordance with 10 CFR 50.59, 10 LFR 50.90 and 10 CFR 50.91, GPU Nuclear Corporation, Operator of the Oyster Creek Nuclear Generating Station, Provisional Operating License No. DPR-16, requests changes to Appendix A of that license.

In accordance with the requirement of the Oyster Creek Technical Specifications GPU Nuclear submitted pressure-temperature (P-T) limits for operation beyond ten (10) effective full power years (EFPY) on January 19, 1988.

The P-T curves were developed based on the surveillance capsule results and on the draft Rev. 2 of Regulatory Guide (R.G.) 1.99. The curves were approved by the NRC staff and were issued on March 21, 1988 as Amendment No. 120 to Oyster Creek Technical Specifications. The current Oyster Creek Technical Specifications require that new P-T operating curves be developed for operation beyond 15 EPPY.

Subsequently, GPU Nuclear evaluated P-T limite using the calculational methods given in the final Rev. 2 of R.G. 1.99. The purpose of this evaluation was to identify the impact of the R.G. 1.99, Rev. 2 on the current P-T curves. The results of this evaluation was submitted by our letter dated July 26, 1989 in response to Generic Letter 88-11, "NRC Position on Radiation Embrittlement of Reactor Vessel Materials and its Impact on Plant Operations."

l The July 26, 1989 letter stated that another set of P-T operating curves for the Oyster Creek reactor vessel would be implemented by the end of 13R (May 1991). This plan complies with the schedule set forth in Generic Letter j 88-11 which required licensees to update and fully implement new P-T curves

]

within two (2) plant outages (approximately 3 years) after the effective date (May 1988) of Pevision 2 to Regulatory Guide 1.99, " Radiation Embrittlement of l Reactor Vessel. Materials." l

]

P{1150015910111ADOCK 03000219 /

PDR ff GPU Nuclear Corporation is a subsidiary of General Pubhc Utilities Corporat;on f 4+- (( g

- .. ,. --. . .-.-= .-- - - . - .~. - - - - . - .- - - -. -_

C331-91-2006-Page 2 This TSCR proposes new pressure-teniperature limite up to 17 EFPY and a new minimum boltup temperature for the vessel closure head stud tensioning.

The new P-T limits-were developed recently in accordance with 10 CFR 50, Appendix G to assure that brittle fracture of the reactor vessel is prevented.

Part of the-analysis involved-in developing the P-T curves is to account for irradiation embrittlement effects in the core region, or beltline. The method described in R.G. 1.99, Rev. 2 was used to account for irradiation embrittlement.

The proposed minimum boltup temperature was determined after comparing results of.the evaluations based on the current and the original Code requirements. A more conservative value of the two results is being proposed.

Detailed discassions on methodology and results of the analyses for generating the P-T limite-and the boltup temperature are provided in the attached report, SASR 90-89, " Pressure-Temperature Curves per Regulatory Guide 1.99, Revision 2 for the Oyster Creek Huclear Generating Station."

It is requested that the amendment authorizing this change become effective prior to restart of Oyster Creek for the cycle 13 operation.. We have

' determined that a timely approval of this technical specification change request will help. reduce duration of the upcoming refueling outage.

This Technical Specification Change Request has been reviewed in accordance with Section 6.5 of the Oyster Creek Technical Specifications.

Pursuant to 10 CFR 50.91(b)( ,, c. copy of this Technical Specification Change Request has been sent to the State of New Jersey Department of Environmental Protection.

Very truly yours, f

.barton Director, Oyster Creek JJB/PFCicrb -

'ce: Administrator, Region I NRC Resident. Inspector (OC)

Mr.-Alex Dromerick, Jr.

(OTSCR*194)-

GPU Nuctent Corporation GPJ MuCleer  ;;sjng;3ce FO'kt"J A'vo'. Now .iorsey 0B7310300 000 071 40'10 Wnto's Dtre::t D:a: Namoor:

Ja ,uar': 11, 1991 Mr. Kent Tosch, Director Bureau of Nuclear Engineering Department of Environmental Protection CN415 Trenton, New Jersey 08625 Dea Mr. Tosch:

Subject:

Oyster Creek Nuclear Generating Station Provisional Operating Licence No. DPR-16 Technical Specification Change Request No. 194 Pursuant to 10CFR50.91(b)(1), please find enclosed a copy of the subject document which was filed with the United States Nuclear Regulatory Comminston on January 11, 1991.

Very truly yourc, JJ , barton Director, oynter Creek JJB/YN/ pip Attachment GPU Nuclear Corporat:on is a subsidiary of Genera! Pubhc Utihtaes Corporation

J s l l

0 l l

I GPU Nuclear Corporation GP ~ Nuclear i

o

"::en:r 888 1 Forked River, New Jersey 087310388 )

609 971 4000 i Wnter's Direct Dial Number.

January 11, 1991 The Honorable Debra Madensky Mayor of Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 Dear Mayor Madensky Enclosed herewith 10 ene copy of Technical Specification Change Request No.

194 for the Oycter Creek Nuclear Generation Station Operating License.

This document was filed with the United States Nuclear Regulatory Commission on January 11, 1991.

Very truly yours, J- _

i[

. %arton Director, oyster Creek JJD/YN/ pip Attachment l

l GPU Nuclear Corporat:on is a subsidaary of General Pubhc Utdities Corporation