ML19289E849

Forwards Tech Spec Change Request 73 Re Incorporation of MAPLHGR Curves.W/Certificate of Svc & Appropriate Class III Fee

ML19289E849
Person / Time
Site:	Oyster Creek
Issue date:	05/24/1979
From:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
To:	Office of Nuclear Reactor Regulation
References
TASK-16, TASK-RR NUDOCS 7905290172
Download: ML19289E849 (3)

Text

b' r

w.; g Jersey Central Power & Light Company

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h Madison Avenue at Punch Bowl Road s

Mornstown, New Jersey 07960 (201)455-8200 May 24, 1979 Director, Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Request for Amendment to Provisional Operating License No. DPR-16 Technical Specification Change Request No. 73 Pursuant to Title 10, Code of Federal Regulations, Section 50.59, three signed originals and fifty-seven conformed copics of Jersey Central Power S Light Company's request for amendment to Appendix A of Provisional Operating License No. DPR-16 for the Oyster Creek Nuclear Generating Station, incorporating Technical Specification Change Request No. 73, are submitted.

The MAPLHGR curves in this Technical Specification Change Request are identical to those provided in Technical Specification Change Request No.

59, dated December 27, 1977, and incorporated in Amendment 30, dated March 14, 1978, with the exception that the Fuel Type V and VB curves have been extended to 30 GWD/MTM. As discussed in my letter of April 30, 1979, the Oyster Creek Station will continue to operate within the more restrie-tive limits of these curves until such time that the analyses are completed to justify operation at higher limits, or a fifth recirculation pump is restored to service.

This Technical Specification Change Request No. 73 has been reviewed and approved by the Station Superintendent, the Plant Operations Review Committee, and the Independent Safety Review Groups in accordance with Section 6.5 of the Oyster Creek Station Technical Specifications.

We have determined that this submittal is Class III in accordance with 10CFR170.22 and have enclosed a check for $4,000 pursuant to that section.

Very truly yours, dW H

/

Ivan R. Fip ro

, Jr.

Vice President 2047 Mi pk Enclosures Jersey Central Power & Light Company is a Memoer o' the Genera! Pubhc U:1 ties SystV9052 90l72

JERSEY CENTRAL POWER 6 LIGHT C0h!PANY OYSTER CREEK NUCLEAR GENERATING STATION Provisional Operating License No. DPR-16 Operating License Change Request No. 73 Docket No. S0-219 Applicant submits by this Technical Specification Change Request No. 73 to the Oyster Creek Nuclear Generating Station Operating License changes to incorporate a new F1APLHGR curve to Section 3.10 of Appendix A.

JERSEY CENTRAL POWER 6 LIGHT C0h!PANY By d97

,4 Vice P si STATE OF NEW JERSEY )

)

COUNTY OF F10RRIS

)

Sworn and subscribed to before ce this 24th day of Flay, 1979.

SM. Li< u ' /$

N 4_w Notary Public PHYLLis A. KA3:3 l'OTARY PUGUC CF NEW EasEy f4C mmics!:, Expira Aag.131973 2047 ?g

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN Tile MATTER OF

)

)

DOCKET NO. 50-219 JERSEY CENTRAL POWER S LIGilT COMPANY )

CERTIFICATE OF SERVICE This is to certify that a copy of Technical Specification Change Request No. 73 for the Oyster Creek Nuclear Generating Station Operating License was filed with the United ctates Nuclear Regulatory Commission on May 24, 1979, and has this 24th <'

of May 1979 been served on the Mayor of Lacey Township, Ocean County

.ew Jersey, by deposit in the United States' mail, addressed as follo.is:

The Honorable Mary Lou Smith Mayor of Lacey Township PO Box 47S Forked River, New Jersey 08731 JERSEY CENTRAL POWER 6 LIGilT COMPANY By 0 &]

p y

Vice Prphid t

DATED: May 24, 1979 2047 263

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Jersey Central Power & Light 'ompany r

q Madison Avenue at Punch Bowl Road 73 g,y;

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Morristown, New Jersey 07960 (201)455-8200 Flay 24, 1979 The lionorable h!ary Lou Smith h!ayor of Lacey Township PO Box 475 Forked River, New Jersey 08731

Dear h!ayor Smith:

Enclosed is one copy of Technical Specification Change Request No. 73 for the Oyster Creek Nuclear Generating Station Operating License.

This document was filed with the United States Nuclear Regulatory Commission on h!ay 24, 1979.

Very truly yours,

$N Ivan R. Finfr k,

r.

Vice Preside t pl Enclosure 2047 264 Jersey Centra! Power & Light Company is a Memoer o+ the General Pubhc Util ties System

Jersey Central Power & Ught Company

. j h*m{/ (f ( )

Madison Avenue at Punch Bowl Road r

,4,C Mornstown, New Jersey 07960 (201)455-8200 May 24, 1979 The lionorable Mary Lou Smith Mayor of Lacey Township PO Box 475 Forked River, New Jersey 08731

Dear Mayor Smith:

Enclosed is one copy of Technical Specification Change Request No. 73 for the Oyster Creek Nuclear Generating Station Operating License.

This document was filed with the United States Nuclear Regulatory Commission on May 24, 1979.

Very truly yours, 38 VicePresir/foc-Ivan R. Fin Jr.

ent pk Enclosure 2047 165 Jerse, Centra! Power & Light Company is a r. e oe c' the Genera Puboc Ut.ht.es System

JERSEY CENTRAL POWER 6 LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE DPR-16 (DOCKET NO. 50-219)

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

1.

Section to be Changed:

Section 3.10 2.

Extent of Changes:

Return MAPLHGR limits for Types

'I.

IIIE, IIIF, V, and VB to those in Amendment 30 and extend them.

3.

Changes Requested:

See attachment 4.

Discussion:

This Technical Specification Change Request is submitted as a demonstration of continued compliance with the requirements of 10CFR50.46. This request would lower the MAPLHGR limits for all fuels to those specified in Amendment 30 and extend the curves for 8x8 fuel to 30 GWD/MTM. The ECCS evaluation models useu for the above changes are the same models used to calculate the Amendment 30 bnPLHGR limits.

The FMPLHGR curves of Amendment 30 and supporting technical basis for four (4) pump operation, presented in our February 6,1976 Ictter remain applicable to the current core configuration. The GE blowdown analysis portion of the previous model used as the basis for these conclusions is insensitive to either fuel design, core configuration, or the number of active flow loops. The previous blowdown model utilized gross core power and flow to determine critical event times; e.g.,

time of rated spray, to be utilized in the respective fuel heatup analyses by GE and Exxon.

With the same core power and flow conditions, no difference in blowdown characteristics would be observed for changes in core configuration or the number of flow loops in service provided the minimum flow is achieved. The latter requirement is assured by current Technical Specification, Section 2.3, Limiting Safety System Settings, for the flow-biased scram curve. Consequently, operation of the plant within the MAPLHGR lirits of Amendment 30 assure compliance with the requirements of 10CFR50.46 and Appendix K, with either four (4) or five (5) pumps in operation.

2047 166

. 4.

Discussion (continued):

The previously docketed transient and accident analyses bound the operation of Oyster Creek with four (4) recirculation loops in operation. Since design flow rate is achieved with four (4) pumps in service, the current Technical Specification power-flow and thermal-hydraulic limits remain applicable. All transients and accidents would have the same initial conditions since the same power and flow relationships would exist as for five (5) pump operation.

The only transients which could result in different system response, with four (4) versus five (5) pump operation, are those in the recirculation system malfunction category.

In particular, the following transients were considered:

1.

All recirculation pumps trip 2.

Single recirculation pump trip 3.

Single recirculation pump stall (pump seizure)

FDSAR Amendment No. 76 addressed each of these events for five (5) pump operation.

There it was shown that the five (5) pump trip was more severe than the one (

pump trip, although both were relatively mild transients. Since the pump coastdown characteristics would be the same with either four (4) or five (5) pumps in service, the five (5) pump trip analysis would still bound both the four (4) pump trip event and the one-of-four pump trip cases.

It was also shown in FDSAR Amendment No. 76 that the one-of-five pump stall was another relatively mild event with results similar to the five (5) pump trip transient. Although the comparison of the responses in the two events was on a critical-heat-flux basis, the same conclusion would be drawn on a critical-power basis.

In the case of a one-of-four pump stall transient, the results would be expected to be slightly more severe than the one-of-five event due to the larger flow / power change. Howevel, the resulting reduction in critical power ratio is readily bounded by observing the sensitivity of critical power ratio to flow rate. The attached figure shows this relationship for an Exxon 8x8 fuel assembly in Oyster Creek operating at design power peaking conditions. As can be seen, percent reduction in critical power ratio is considerably less than given percent change in flow rate over the entire range considered.

Therefore, assuming a 5% reduction in critical power as a result of the 5% flow difference between a one-of-four pump stall and the one-of-five event is very conservative. This 2h047 167

. 4.

Discussion (continued):

approach is additionally conservative since it ignores the power reduction due to higher void generation that would result in the one-of-four pump stall event.

Therefore, a bounding value of MCPR during a one-of-four pump stall was developed as follows:

A MCPR

.01 For one-of-five pump stall (based upon comparison of five (5) pump trip and one (1) pump stall analyses of FDSAR Amendment No. 76).

.07 Conservatively assumed as difference between one-of-four and one-of-five pump stalls.

.08 Bounding change in MCPR for one-of-four pump stall.

Consequently, with a steady-state value of 1.52, the bounding MCPR for a one-of-four pump stall would be 1.44 and there would remain substantial margin to the transient limit of 1.34.

There-fore, it is concluded that the one-of-four pump stall is not a limiting MCPR event and is bounded by the continuous rod withdrawal error event which in previously docketed information was shown to be the limiting MCPR ever.t.

2047

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.039 If at any time during operation it is determined by normal surveillance that the limiting value for LHGR is being exceeded, action shall be initiated to restore operation to within the prescribed limits.

If the LHGR is not returned to within the prescribed limits within two (2) hours, action shall be initiated to bring the reactor to the cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

During this period, surveillance and corresponding action shall continue until reactor operation is within the prescribed limits at which time power operation may be continued.

C.

Assembly Averaged Power Void Relationship During power operation, the assembly average void fraction and assembly power shall be such that the following relationship is satisified:

1-VF (PR x FCP

)

B Where:

VF

= Bundle average boid fraction PR

= Assembly radial power factor FCP = Fractional core power (relative to 1930 MWt)

B

= Power-Void limit The limiting values of "B" for each fue; type are shown in the table below:

Fuel Type (s)

B I, II, III

.365 IIIE, IIIF

.377 V, VB

.332 D.

Minimu:.1 Critical Power Ratio (MCPR)

During stesdy state power operation, MCPR shall be greater than or equal tr the following:

ARPM Status MCPR Limit 1.

If any two (2) LPRM assemblies which 1.64 are input to the APRM system and are separated in distance by less than 2047 170

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