ML20002A361

Submits Proposed Change 125,Suppl 5,to Tech Specs,Replacing Pages Submitted in 750714 Proposed Change 125 & 751010 Proposed Change 125,Suppl 1.Proposes Restriction of Core Thermal Performance,Pending Approval of Analysis Results

ML20002A361
Person / Time
Site:	Yankee Rowe
Issue date:	11/26/1975
From:	Vandenburgh D YANKEE ATOMIC ELECTRIC CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20002A362	List: ML20002A361 ML20002A363
References
WYR-75-138, NUDOCS 8011140293
Download: ML20002A361 (8)

Text

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3,,w (7ropor:d Ch;ng2 N3. 125

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( iuppitm:nt No. 5 Telephone 617 366-9011

'EEGUL!_TC2Y DOSHILE COP.YJJ m

710 390 0739 YANKEE ATCh110 ELECTRIC COMPANY WrR,5-12e

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20 Turnpske Road Westborough, Massochusetts 01581 t

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November 26, 1975 i

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United States Nuclear Regulatory Commission

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Washington, D. C.

20555 fy Attention: Office of Nuclear Reactor Regulation

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Reference:

(1)

License No. DPR-3 (Dockt.t No. 50-29)

CD D

(2)

Proposed Change No.125 (July 14,1975)

(3)

Proposed Change No. 125, Supplement No. 1, MillN,'

(October 10, 1975) gN

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(4)

Proposed Change No. 125, Supplement No. 2, g

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(October 28, 1975) fj,3 (5)

Proposed Change No. 125, Supplement No. 3, f.]

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(November 7, 1975)

(6)

Proposed Change No. 125, Supplement No. 4, h

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(November 20, 1975)

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Subject:

Core XII LOCA Analysis

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Dear Sir:

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Pursuant to Section 50.59 of the Cormission's Rules and Fagulations, Yankee Atomic Electric Company hereby preposes the following modifications

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to Appendix A to the Technical Specifications:

tj PROPOSED CHANGE:

It is proposed that the attached revised pages replace 3

those previously submitted in Reference 2 and 3.

In addition, the attached Appendix B should be added to the report.

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PIASON FOR CHANGE: The evaluation model previously used to perform a LOCA

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analysis for Core XII (see Reference 3) has been modified as requested by a

the NRC staff on November 17, 1975 and a supplementary analysis has been 2

performed. The revised evaluation model and the results obtained are described in Attachment B to this letter. Results indicate that reduced peak linear heat rates are required in order to comply with the ECCS performance criteria of 10CFR50.46. Thus, an interim technical specifi-cation, restricting core thermal performance, is proposed for Core XII

/

operation until less restrictive LOCA analysis results are approved.

The proposed interim technical specification also describes the manner I

in which core thermal performance will be monitored.

i SAFETY CONSIDERATIONS: Based on the considerations in Proposed Change j

No. 125 as modified by Supplements No. 1 through 5, it is concluded that 1

j

.80.n y agy 13413 j

United States Nuclear Rcgulatory Commission November 26, 1975 Attn Office of Nuclear Reactor Regulation Page Two Core XII operation within the proposed specifications will not endanger the health and safety of the public.

This proposed change has been reviewed by the Nuclear Safety Audit and Review Committee.

SCHEDULE OF CHANGE: The Core XII startup is schedulgd to commence on December 1, 1975. We respectfully request review of this Propcsed Change by the Co= mission as soon as practical.

Any questions regarding this Proposed Change should be directed to Mr. Alan E. Ladieu at our Engineering Office, 20 Turnpike Road, Westboro, Massachusetts, 01581, (617) 366-9011, Extension 2845.

Respectfully submitted, YANKEE ATOMIC ELECTRIC COMPANY t

D. E. Vandenburgh d

Vice President COS*MOUWEALTH OF MASSACHUSE'ITS)

)ss.

COUNTY OF WORCESTER

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I Then personally appeared before me, D. E. Vandenburgh, who, being. duly

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sworn, did state that he is Vice President of Yankee Atomic Electric Company, that he is duly authorized to ex u te and file the foregoing request in the name and on the behalf of Yankee #.tomic. Electric Company, and that the j

statements therein are true to the best of his knowledge and belief.

CW b

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f Armand R. Soucy Notary Public My Commission Expires September 9, 1977 l

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O oV TABLE OF CONTENTS (Con't.)

Page No.

7.3 CONTROL ROD DROP INCIDENT 48 49 7.4 ISOLATED LOOP STARTUP INCIDENT 7.5 LOSS OF LOAD INCIDENT,

49 7.6 LOSS OF FEEDWATER FLOW INCIDENT 49

-7.7 LOSS OF COOLANT FLOW INCIDENT 49 7.8 CONTROL ROD EJECTION ACCIDENT 50 7.9 STEAM LINE RUPTURE ACCIDENT 50 7.10 STEAM CENERATOR TUBE RUPTURE ACCIDENT 50 7.11 LOSS OF COOLANT ACCIDENT 50 7.12 OTHER ACCIDENTS AND TRANSTENTS 50

8.0 PROPOSED CHANGE

S TO TECHNICAL SPECIFICATIONS 54 9.0 STARTUP PROGRAM 55

10.0 REFERENCES

56 APPENDIX A: LOSS OF COOLANT ACCIDENT ANALYSIS 57 APPENDIX B: ADDITIONAL LOCA ANALYSIS 71 W

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8.0 PROPOSED CHANGE

S TO TECHNICAL SPECIFICATIONS It _is requested that the following revisions be made to the Technical Specifications.

Section B.

DESIGN SPEt'IFICATIONS Add the following paragraph:

"3.

The Performance Analysis for the current reload core is incorporated as a p' art of these technical specifications.

The analysis presented in the FSAR for Core XI forms the basis for the reference core performance analysis".

Section D.

OPERATING PR9CEDURES AND RESTRICTIONS 2.

Operating Limits

_ Thermal c.

Revic,e paragraph (1) to read as follows:

" (1) During steady state power operation, the peak linear heat rate shall not exceed the limits shown in Figure 8-1.

With these limits, if full power cannot be attained, the allow-able-fraction of full power shall be calculated as follows:

Allowable Fraction of Full Power =;Pe 11 P LHGR where the limiting LHGR is obtained from Figure 8-1.

The peak full power LHGR shall include the following:

)

a) Heat flux power peaking factor, F measured using core instrumentation at a power p_ 10%;

b) Effect of inserting the control bank from its position at the time of measurement to its insertion limit (F ) as I

show. In Figure 8-2.

The rod insertion limit is shown in Figure 8-3; c) Effect of xenon redistribution (1,10);

d)

Flux peaking augmentation factor (power spike) using Figure 8-4:

e) Shortened stack height factor (1.009);

)

y; f) Measurement uncertainty (1.05);

g) Power icvel uncertainty (1.03);

h h) Heat flux engir.cering factor, Fk, (1.04);

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Corc average linear heat generation rate at full j

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power (4.34 kw/ft),

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These factors are multiplicative and items (a) and (d) shall be chosen at a core height so as to maximize their product. When operating at constant power, all rods out, with equilibrium xenon, power peaking in the Yankee Rowe core decreases monotonically as a function of cycle burnup. This has been verified by both calcu-lation and measurement on Yankee cores and is in accord with the expected behavior in a core that does not contain burnabic poison.

The all-rods-out power peaking meas'ured at any time in core life.thus provides an upper bound on ARO power peaking for the' remainder of that cycle. Therefore, the measured power peaking shall be checked every 1000 equivalent full power hours and the latest measured value shall be used in the computation. The only effects which can increase peaking beyond this value would be control rod insertion and xenon transients and these are accounted for in items (b) and (c).

These proposed changes reference this report as the performance analysis for the current reload core while retaining the performance The section on core thermal analysis for the reference core in the FilSR.

performance is also changed to reflect the results of the LOCA analysis and to describe the manner in which core thernial performance will be monitored. No other changes are required.

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