ML20067B711
| ML20067B711 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/09/1994 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20067B697 | List: |
| 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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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
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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 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: !
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- 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. '
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- 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
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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.
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/g > The licensee.shall operate _the facilityj n_accordance with the
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s Technical Specifications.
~Jga g noe py, .. na a . s a..e t-J A - - d- - ts, ; 3 C. R5E3Fds l
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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 <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, -j
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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 [ 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
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shell temperature differential shall not exceed 145'F.
locations taken over a 45 minute 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 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, .
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'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:
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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
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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