Text

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)
	v • d • e

- -- -

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless the loop is sooner ;

returned-to service.

i t

I l

t

[

l i

I

_ I i

9402250064 940209 PDR ADOCK 05000293 P PDR i.c Amendment No. 148, l

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

1 Applies to the operating status of Applies to the periodic examination l the reactor coolant system. and testing requirements for the l 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 l

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

~

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 operation shall not be permanently logged at least I 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 l 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 {

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. 285 -82,-140, 123

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: !

?

1. The force that initiates free movement of the ?

snubber rod in either tension or compression is :

less than the specified 1 maximum drag force. '

'l ;

i

3. Snubber Service Life Monitorina ]

A. A record of the service life '

Amendment No.-60 1 137c l

ATTACHMENT C

- Marked-up Existina Technical Specification Paces i i

i License Page 3 4 Appendix A Page 123 i Appendix A Page 137c T

4 i

1 I

'I J

f e

r

4

~

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

\

s Technical Specifications.

~Jga g noe py, .. na a . s a..e t-J A - - d- - ts, ; 3 C. R5E3Fds l

~

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

D. Eoualizer Valve Restriction - DELETED E. Recirculation loop Inoperable l The reactor shall not be operated with one recirculation loop;out of '

service for more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless the loop is sooner returned to service.

I 1 l

I

.l l

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

, , , _ . _ ._. . .~ . . _ . . ._._____.I

, 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 [ t not exceed 100*F/hr when averaged temperatures at the following l l over a one-hour period except locations shall be permanently logged at least every 15 minutes J l when the vessel temperatures are /

above 450*F. The reactor vessel flangetoadjacentreactorvessel(My until the difference between any two readings at individual

/

shell temperature differential shall not exceed 145'F.

locations taken over a 45 minute period is less than 5'F:

f}l} 1

[

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 I and/or leakage tests, a(d A hl"*b head, and reactor coolant pressure p[? -

i critical core operation sfal h ot j shall be permanently logged at be conducted unless the reactor least every 15 minutes wh1never the vessel temperatures are above },. shell temperature is below 220*F those defined by the appropriate and the reactor vessel is not :

curves on Figures 3.6.1, 3.6.2, /. 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 . reactor vessel adjacent to the 1

shell as shown in Figures 3.6.1 1 vessel wall at the core midplane

and 3.6.2. ') level. The specimens and sample .

program shall conforin to the l

Revhion-157P ic 123 i Amendment No.pB 2 , MO',

$3, .

4 1

'a I 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- l cally required not to J displace under contin- l uous load, the ability l of the snubber to with- l stand load without dis- !

placenent shall be veri-fied.

C. Mechanical Snubbers Tunctional Test Acceptance Criteria !

The mechanical snubber functional test shall verify that:

~

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 '

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 60~~, 137c Amendment No

ML20067B711

Text

Navigation menu

Search