ML20067B711

Proposed Tech Specs Revising Wording for Page 3 of License DPR-35,clarifying Words to Aid Operators & Removing Obsolete Mechanical Snubber Acceptance Criterion

ML20067B711
Person / Time
Site:	Pilgrim
Issue date:	02/09/1994
From:	BOSTON EDISON CO.
To:
Shared Package
ML20067B697	List: ML20067B694 ML20067B711
References
NUDOCS 9402250064
Download: ML20067B711 (7)

Text

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j B.

Technical Snecifications The Technical Specifications contained in Appendix A, as revised i

by NRC approved and docketed Amendments, are hereby incorporated in l the license. The licensee shall operate the facility in accordance with the Technical Specifications.

C.

Records Boston Edison shall keep facility operating records in accordance with the requirements of the Technical Specifications.

D.

Equalizer Valve Restriction - DELETED E.

t;irculation Loon Inonerable The reactor shall not be operated with one recirculation loop out of service for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

With the reactor operating, if one recirculation loop is out of service, the plant shall be placed in a f

hot shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the loop is sooner returned-to service.

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i 9402250064 940209 PDR ADOCK 05000293 P

PDR i.c Amendment No. 148,

LIMITING CONDITION FOR OPERATION SURVEILLANCE RE0VIREMENTS 3.6 ERIMARY SYSTEM BOUNDARY 4.6. PRIMARY SYSTEM BOUNDARY Applicability:

Applicability:

Applies to the operating status of Applies to the periodic examination the reactor coolant system.

and testing requirements for the reactor cooling system.

Ob.iective:

Ob.iective l

To assure the integrity and safe To determine the condition of the operation of the reactor coolant reactor coolant system.and the i

system operation of the safety devices related to it.

Epecification:

Specification:

A.

Thermal and Pressurization A.

Thermal and Pressurization Limitations Limitations 1.

The average rate of reactor 1.

During heatups and cooldowns, coolant temperature change with the reactor vessel during normal heatup or temperature less than or equal cooldown shall not exceed to 450 F, the temperatures at l

100 F/hr when averaged over a the following locations shall one-hour period except when the be permanently logged at least vessel temperatures are above every 15 minutes until the 450"F. The reactor vessel difference between any two flange to adjacent reactor readings at individual vessel shell temperature locations taken over a 45 i

differential shall not exceed minute period is less than 5 F:

145 F.

a. Reactor vessel shell l

adjacent to reactor vessel flange

b. Reactor vessel shell flange

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c. Recirculation loops A and B 2.

The reactor vessel shall not be 2.

Reactor vessel shell pressurized for hydrostatic temperatures, including reactor I

and/or leakage tests, and vessel bottom head, and reactor i

subcritical or critical core coolant pressure shall be 4

I operation shall not be permanently logged at least conducted unless the reactor every 15 minutes whenever the l

vessel te.mperatures are above shell temperature is below i

those defined by the 220 F and the reactor vessel is appropriate curves on Figures not vented.

3.6.1, 3.6.2, and 3.6.3.

4 (Linear interpolation between Test specimens of the reactor curves is permitted). At vessel base, weld and heat stated pressure, the reactor affected zone metal subjected vessel bottom head may be to the highest fluence of maintained at temperatures greater than 1 Mev neutrons

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below those temperatures shall be installed in the corresponding to the adjacent reactor vessel adjacent to the reactor vessel shell as shown vessel wall at the core in Figures 3.6.1 and 3.6.2.

midplane level.

The specimens j

and sample program shall conform to the Amendment No. 28 -82,-140, 123 5

L}MITING CONDITIONS FOR OPERATION 4.6.I Shock Suppressors (Snubbersl f

Specification 4.6.1.2.B, or 4.6.I.2.0, as applicable, an additional 10% of that type-of snubber shall be functionally tested.

B. General Snubber Functional-l Test Acceptance Criteria (Hydraulic and Mechanical)

The general snubber functional test shall verify that:

1._ Activation (restraining action) is achieved within the specified range of velocity or acceleration.in i

both tension and compression.

2. Snubber release, or bleedrate, as applicable, where required, is within the specified range in compression or tension.

For snubbers specifically i

required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

L. Mechanical Snubbers Functional Test Acceptance Criteria j

The mechanical snubber functional test shall verify i

that:

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1. The force that initiates free movement of the

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snubber rod in either tension or compression is less than the specified 1

maximum drag force.

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3.

Snubber Service Life Monitorina

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A. A record of the service life Amendment No.-60 137c 1

ATTACHMENT C Marked-up Existina Technical Specification Paces i

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License Page 3 4

Appendix A Page 123 i

Appendix A Page 137c T

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B.

Technical Specifications 1

The Technical Specifications contained in Appendix A, as revised through-Amendment-No -ISOP are hereby incorporated in the license.

l g > The licensee.shall operate _the facilityj n_accordance with the

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Technical Specifications.

3 s ~Jg g noe py,.. na a. s a..e t-J A - - d- - ts, ;

a C.

R5E3Fds Boston Edison shall keep facility operating records in accordance

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with the requirements of the Technical Specifications.

D.

Eoualizer Valve Restriction - DELETED E.

Recirculation loop Inoperable The reactor shall not be operated with one recirculation loop;out of service for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With the reactor operating, if one recirculation loop is. out of service, the plant shall be placed in a hot shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the loop is sooner returned to service.

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.l Revision-169 9" Amendment-No. 150,

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1JHTTING CONDITXON FOR OPERATION SDRVEILLANCE REQUIREMENTS 3.6. PRIMARY SYSTEM BOUNDARY 4.6.

PRIMARY SYSTEM BOUNDARY Apolicability:

Aeolicability:

Applies to the operating status of the Applies to the periodic examination and reactor coolant system.

testing requirements for the reactor cooling system.

Qbiective:

Ohitctive:

To assure the integrity and safe To determine the condition of the operation of the reactor coolant system reactor coolant system and the operation of the safety devices related to it.

Soecification:

Specification:

A.

Thermal and Pressurization A.

Thermal and Pressurization Limitations Limitations 1.

The average rate of reactor 1.

During heatups and cooldowns, with p coolant temperature change during the reactor vessel temperature less l

normal heatup or cooldown shall than or equal to 450*F, the

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t not exceed 100*F/hr when averaged temperatures at the following l

l over a one-hour period except locations shall be permanently J

l when the vessel temperatures are /

logged at least every 15 minutes above 450*F.

The reactor vessel until the difference between any

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flangetoadjacentreactorvessel(My two readings at individual f}l}

shell temperature differential locations taken over a 45 minute 1

shall not exceed 145'F.

period is less than 5'F:

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a.

Reactor vessel shell adjacent f

b to reactor vessel flange g

b.

Reactor vessel shell flange l

c.

Recirculation loops A and B 2.

The reactor vessel shall not-bem,2.

Reactor vessel shell temperatures, pressurized for hydrosta. tic including reactor vessel bottom p[?

I and/or leakage tests, a(d A hl"*b head, and reactor coolant pressure critical core operation sfal h ot shall be permanently logged at i

j be conducted unless the reactor least every 15 minutes wh1never the

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vessel temperatures are above shell temperature is below 220*F those defined by the appropriate curves on Figures 3.6.1, 3.6.2,

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and the reactor vessel is not vented.

and 3.6.3.

(Linear interpolation h between curves is permitted). At Ij Test specimens of the reactor stated pressure, the reactor jj vessel base, weld and heat affected vessel bottom head may be l

zone metal subjected to the highest maintained at temperatures below I

fluence of greater than i Hev

.those temperatures corresponding i

neutrons shall be installed in the to the adjacent reactor vessel 1

. reactor vessel adjacent to the shell as shown in Figures 3.6.1 1

vessel wall at the core midplane and 3.6.2.

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level.

The specimens and sample program shall conforin to the l

Revhion-157P ic Amendment No.pB 2, MO',

123 i

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SURVEILLANCE RIQUIREMINT LIMITING CONDITION FOR OPERATION 4.6.1 Shock Suppressors (Snubbers)

Specification 4.6.I.2.B. or i

4.6.I.2.C. as applicable, an additional 10% of that type of snubber shall be functionally tested.

B.

General Snubber Functional Tes t Acceptance Criteria (Hydraulic and Mechanical)

The general snubber functional test shall verify that:

1.

Activation (restrain-ing action) is achieved within the specified range of velocitv or acceleration in both tension and compression.

2.

Snubber release, or bleed-rate, as applicable, where required; is within the specified range in compression or tension.

For snubbers specifi-cally required not to J

displace under contin-uous load, the ability of the snubber to with-stand load without dis-placenent shall be veri-fied.

C.

Mechanical Snubbers Tunctional Test Acceptance Criteria The mechanical snubber functional test shall verify that:

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1.

The force that initiates free movement of the l

snubber rod in either tension or compression is less than the specified i

maximtun drag force.f1Ir~aP '

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p illg ot have inc-reased more than 50% since 4he'last functi M al J sh.-

3.

S_nubber Service Life Monitoring A.

A record of the service life 137c Amendment No 60~~,