ML20090L915

Application for Amend to License DPR-16,consisting of License Amend Request 207,changing TS 4.2.E.5 Re B-10 Enrichment Surveillance of Standby Liquid Control Sys to Once Every 24 Months

ML20090L915
Person / Time
Site:	Oyster Creek
Issue date:	03/17/1992
From:	J. J. Barton GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20090L918	List: ML20090L915 ML20090L923
References
207, C321-92-2056, NUDOCS 9203230328
Download: ML20090L915 (9)

Text

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Peggeny, New Jerser 07054 201 310 7000 TELEX 136-482 Writere Direct Del Nurntier March 17, 1992 C321-92-2056 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:

Subject:

Oyster Creek Nuclear Generating Station c t bpra g License Amendment Request No. 207 Pursuant to 10 CFR 50.90, GPU Nuclear Corporation, operator of the Oyster Creek Nuclear Generating Station (OCNGS), facility Operating License No. DPR-16, requests a change to that license.

Technical Specifiestion (TS) 4.2.E.5 requires a D-10 enrichment surveillance of the Standby Liquid Control System at each refueling outage with analyses available within 30 days after startup. Since OCNGS procures the sodium pentaborate pre enriched (B-10) and the B 10 is very stable, this TS unduly restricts the perfomance of this surveillance to a plant shutdown. In order to allow flexibility in the master surveillance schedule, OCNGS proposes to change the surveillance interval to once every 24 months.

This change request has been reviewed in accordance with Section 6.5 of the OCNGS Technical Specifications, and using the standards in 10 CFR 50.92 we have concluded that this proposed change does not constitute a significant hazards consideration.

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Page 2 C321 92-2056 Pursuant to 10 CFR 50.9)(b)(1), a copy of this change request has been sent to the State of New Jersey Department of Environmental Protection, ry u au s, ,

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Parts)pa,iv. New Je,sey 07054 701 316 7000 TELEX 136 482 W,itet a Dweet omi Number March 17, 1992 Mr. Kent Tosch, Director Dureau of Nuclear Engineering Department of Environmental Protection CN 411 Tranton, NJ 08625

Subject:

Oyster Creek Nuclear Generating Station Facility Operating License No. DPR-16 Facility Operating License Amendment Request No. 207 Pursuant to 10 CFR 50.91(b)(1), please find enclosed a copy of the subject document which was filed with the United States Nuclear Regulatory Commission on March 17,1992.

ery truly yours,

- - f &O J. Barton President and Director Oyster Creek JJB/DGJ/ pip L

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o- u- e- a-Parswany, New Jersey 01054 201 316 7000 TELEX 130 482 Wnter's Direct Dal Nurrber March 17,1992 1he Honorable Russell C. Palumbo Mayor of Lacey Township .

818 West Lacey Road forked River, NJ 08731

Dear Mayor Palumbo:

Enclosed herewith is one copy of facility Operating License Amendment Request No.

207 for the Oyster Creek Nuclear Generating Station Operating License.

This document was filed with the United States Nuclear Regulatory Comission on March 17, 1992.

Very truly yours, f -

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e' dent and Director ster eek Attachment JJB/DGJ/ pip GPU Nuclear Corporation is a subscary of General Public Utihtien Corporation V

GPU i;UCLEAR CORPORATION OYSTER CREEK NUCLEAR GE!1LRATING STA110f1 facility Operating License No. DPR-16 Facility Operating License Amendment Request No. 207 Docket No. 50-219 Applicant submits, by this f acility Operating License Amendment Request No. 207 to the Oyster Creek Nuclear Generating Station Operating License, a change to pages 4.2-2 and 4.2-4.

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[J. RB/rton VMe Vresident and Director Oyster Creek SwornandSubscribedtobeforemethis/ day o h d 1992.

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o UN11ED STATES OF AMERICA NUCLEAR REGULA10RY COMMISSION  ;

1 In the Matter of '

Docket No. 50 219 GPU Nuclear Corporation CERTlflCATE Of SERVICE This is to certify that a copy of facility Operating License Amendment Request No. 207 for Dyster Creek Nuclear Generating Station Operating L1censo, filed with the U.S. Nuclear Regulatory Commission on March 17, 1992 has this day of March 171992, been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:

The lionorable Russell C. Palumbo Mayor of Lacey Township 818 West Lacey Road forked River, NJ 08731

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l OYSTER CREEK NUCLEAR GENERATING STATION ,

OPERATING LICENSE NO. DPR-16 DOCKET NO. 50 219 LACIllTY OPERATING LICENSE AMENDMENT REQUEST NO. 207 Applicant hereby reouests the Commission to change Facility Operating tii 't-DPR-16 as discussed below, and pursuant to 10 CFR 50.91, an

, n2 mcerning the determination of no significent *azards car also presented:

, . .i0 BE CHANGED 1 Basis 2.0 (U M (,J CHANGE 3ange the surveillance for Boron-10 enrichment to reflect the use of sodium pentaborate preformulated and pre enriched at the vendor's facility.

3.0 CHANGES REQESJfD As delineated on the attached revised Technical Specification pages 4,2-2 and 4.2 '.

4.0 QISfdS$1QRS Paragraph (c)(4) of 10 CFR 50.62, " Requirements for reduction of risk from Anticipated Transients Without Scram (ATWS) events for light-water-cooled nuclear power plants", reqitires that each boiling water reactor must have a Staridby Liquid Control System (SLCS) with a minimum flow capacity -and boron content equivalent in control capacity to 86 gallons per minute of 13 weight percent sodium pentaborate solution. OCNGS meets the equivalency requirements based on a minimum solution concentration of- 15.0 wt. percent, a Boron-10 enrichment of 35 atom percent and a-30 gpm pump flow rate-The approach taken by OCNGS was one of three options approved by the NRC staff as -an acceptable response to the ATWS Rule (Referene.e:

Safety Evaluation of Topical Report NEDE-31096-p, " Anticipated Transient Without Scram; Response to ATWE Rule 10 CFR 50.62,"

trcnsmitted by letter, G. Lainas, NRC, -to T. Pickens, BWR 0wners Group, dated October 21,1986). Associated with this option was a

.equiremert .for surveillance and positive verification of the ct rect Boron-10 enrichment. These surveillances were discussed with the NRC staff during a BWR Owners' Group meeting on April 3, 1987.

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4.0- ElSCUSSIOfLS (Continued)

OCNGS purchases sodium pentaborate preformulated and pr9-enriched at the . vendor's facil:ty. The B-10 enriched sodium pentaborate is procured in accordance with the vendor's quality assurance plan as approved by GPU Nuclear. Samples of batches to be shipped are analyzed prior to shipment by an independent laboratory contracted by GPU Nuclear. Once verification is completed it is only then that

, these batches are shipped to the plant site. The chemical, while in storage or in the SLCS tank, cannot change its B-10 enrichment, l because B-10 is very stable. Since chemicals used in making up the i solution in the SLCS tank are only from these batches, there is no reason why the resulting solution will be below the minimum B-10 l enrichment. Water addition to the tank can change the weight '

percent of the sodium pentaborate solution but cannot change the B-10 enrichment.

ihe current Technical Specification 4.2.E.5 requires the performance of the B-10 enrichment surveillance at each refueling outage with the receipt of the analysis no later than 30 days after startup.

The intent of this surveillance is to provide a periodic ,

verification, at least once per operating cycle, of the B-10 cnrichment as found in the SLCS tank.

Since the samples for the enrichment analysis can be taken from tht.

SLCS tank at any time (power operation, refueling, etc), the current Technical Specification unduly restricts the perfcrmance of this surveillance to plant shutdowns. Further, the B-10 is very stable which precludes a change while in the SLCS tank. Since the intent is to verify the B-10 enrichment once per operating cycle, there is no specific need to restrict this surveillance to only a refueling outage when the surveillance can be performed at any time. Based on these facts, OCNGS proposes to change the surveillance to once every 24 months. This change will retain a defined schedule for the surveillance, but the' change will allow flexibility in performing the sur. veillan. ce._

5.0- DETERMINATION GPU Nuclear has determined that operation of the Oyster Creek Nuclear Generati_ng Station in accordance with the proposed Technical

' Specifications does not involve a significant-hazard. The changes

-do not:

1. Involve a-JJgnificant increase in the probability or the conseauence of an accident orevicusly evaluated.

The proposed changes reflect the use of preformulated and pre-enriche1 sodium pentaborate in the SLCS. .Since the sodium

--pentaborate is independently ve fled for the B-10 enrichment prior-to shipment, an enrichmeat analysis of the SLCS tank once every twenty-four months is deemed adequate to ensure that the reactor can-be brought to-a cold shutdown condition from full power steady state operating conditions at any time

in core life independent- nf control rod system capabilities.

The probability or the consequences of an accident previously

- evaluated are unaltered by-the proposed change.

2. Create the possibjlity of a new or diff_qtenLkind of accident from any previous 1v evaluatqq.

The proposed changes do not modify the system design for the SLCS nor the manner in which the SLCS would be operated.

Since the SLCS retains-the capability to shutdown the reactor, this change does not create the possibility of a new or diiforent kind of accident from any previously evaluated.

3. Ir,volve_A sianificant reduction in a maroin of safety.

The proposed changes allows the performance of the 0-10 enrichment surveillance during power operation. or plant shutdown. Since the frequency of the surveillance stays the same, once per twenty-four months, there is no significant reduction in' the margin of safety. The SLCS retains - the canability to bring the reactor to a cold shutdown condition from full power steady state operating conditions at any time in core life independent of control rod system capabilities.

6.0 IMPLEMENTATION

It is requested that the amendment authorizing this change become effective 60 days after issuance.

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