Text

Proposed Tech Specs,Relocating Table 3.4-1, RCS PIVs from TS 3.4.6.2, RCS Operational Leakage to Techical Requirements Manual
	ML20086R211
Person / Time
Site:	Seabrook
Issue date:	07/24/1995
From:	; NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	;
Shared Package
ML20086R200	List: ML20086R197; ML20086R209; ML20086R211;
References
	NUDOCS 9507310057
	Download: ML20086R211 (10)
	v • d • e

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REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM LEAKAGE OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:

a. No PRESSURE BOUNDARY LEAKAGE,

b. 1 gpm UNIDENTIFIED LEAKAGE,

c. 1 gpm total reactor-to-secondary leakage through all steam generators and 500 gallons per day through any one steam generator,

d. 10 gpm IDENTIFIED LEAKAGE from the Reactor Coola'nt System,

e. 40 gpm CONTROLLED LEAKAGE at a Reactor Coolant System pressure of 2235 psig i 20 psig, and

f. 0.5 gpm leakage per nominal inch of valve size up to a maximum of 5 gpm at a Reactor Coolant System pressure of 2235 20 osio from a olant System Pressure Isolation Valv s dified h Mic 3. 4-1.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With any Reactor Coolant System leakage' greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE and leakage from Reactor Coolant System Pressure Isolation Valves, reduce the leakage rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least two closed manual or deactivated automatic valves, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Test pressures less than 2235 psig but greater than 150 psig are allowed. '

Observed leakage shall be adjusted for the actual test pressure up to 2235 psig assuming the leakage to be directly proportional to pressure dif-ferential to the one-half power.

SEABROOK - UNIT 1 3/4 4-21 h

9507310057 950724 PDR P ADOCK 05000443 PDR

l REACTOR C00LANT SYSTEM REACTOR COOLANT SYSTEM LEAKAGE

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OPERATIONAL LEAKAGE

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SURVEILLANCE REQUIREMENTS 4.4.6.2.2 Coolant System Pressure Isolation Valve - :d k.

.. _ shall be demonstrated OPERABLE by verifyi e o s limit:

a. -At least once per 18 months, ~

b. Prior to entering MODE 2 whenever the plant has been in COLD.

SHUTDOWN for 7 days or more and if leakage testing has not been . 'l perfomed in the previous 9 months,

c. Prior to returning the valve to service following maintenance, repair, or replacement work on the valve, and

d. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve.

e. As outlined in the ASME Code,Section XI, paragraph IW-3427.(b). ,,_,

The provisions of Specification 4.0.4 are not applicable for. entry into MODE 3 or 4.

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SEABROOK - UNIT 1 3/4 4-23 Amendment No.-30

I fM5 ~DJTErJTmA) ALLi 8LAeJK T'.0LC 3.4 1-

-REACTORmT--SY& TEM-PRESSURE-450 TAT 10fMtAtVES VALVE VALVE NUMBER SIZE MAX. ALLO ABLE-FUNCTION LEAKAGE GPM)

SI-V144 1-1/2" SI to RCS Loop 1 Cold-Leg Inje: tion .75 SI-V148 1\1/2" SI to-RCS Loop 2 Cold-Leg Injection 0.75 SI-V152 1-1/2" SI to RCS Loop 3 Cold-Leg Injection 0.75 Si-V156 1-1/2" SI to RCS Loop 4 Cold-Leg Injection 0.75'

! SI-V81 2" N\

SI to RCS Loop 3 Hot-Leg Injection- 1. 0 SI-V86 2" \ 51 to RCS Loop 2 Hot-Leg Injection 1.0 SI-V106 SI-V110 2"

2"

\ SI to RCS Loop 4 Hot-Leg Injection 1. 0 SI-V118 2"

\\ SI to RCS Loop 1 Hot-Leg Injection 1. 0 SI to RCS Loop 1. Cold-Leg Injecpion 1. 0 SI-V122.. 2" \SI to RCS Loop 2 Cold-Leg Inj9ction 1. 0 SI-V126 2" SI-V130 2" SItoRCSLoop3 Cold-LegInjection 1. 0 S1 RCS Loop 4 Cold-Leg njection 1. 0 SI-V140. 3" SI t RCS Cold-Leg Inje ion- 1.5 SI-V82 6" SItoRDSLoop3 Hot SI-V87 6" gInjection 3.0 SI to RCS\ Loop 2 Hot, Leg Injection 3.0 RH-V15 6" RHR to SI toop 1 Cold-Leg Injection RH-V29 6" 3.0 RHR to SI Loop A old-Leg Injection 3.0 RH-V30 6" RHR to SI Loo Cold-Leg Injection RH-V31 6" 3.0 RHR to SI Loo Cold-Leg Injection 3. 0 RH-V52 6" SItoRCSLooplyot-LegInjection RH-V53 6" 3.0 !

SI to RCS L6op 4 Rot-Leg Infection 3.0 RH-V50 8"

/ \

RHR to CS Loop 4 HotqLeg Injection 4. 0 RH-V51 8" RHR t CS Loop 1 Hot-leg Injection 4.0 SI-V5 10" SI $ RCS Loop 1 Cold-Le ' Injection SI-V6 5. 0 10" SI/ Tank 9A Discharge Isola ion 5. 0 SI-V20 10" Si to RCS Loop 2 Cold-Leg I jection SI-V21 10" 5.0 SI Tank 98 Discharge Isolatio 5.0 SI-V35 10" SI to RCS Loep 3 Cold-Leg Inje ion SI-V36 10" 5.0 SI Tank 9C Discharge Isolation 5. 0

~SI-V50 10" SI to RCS Loop 4 Cold-Leg Injecti SI-V51 10" 5.0 SI Tank 9D Discharge Isolation 5.0 RC-V22* 12" RHR Pump BA Suction Isolation RC-V23* 12" 5.0 RHR Pump 8A Suction Isolation 5. 0 RC-V87* 1 RHR Pump 8B Suction Isolation 5.0 RC-V88* )" RHR Pump 8B Suction Isolation 5. 0

/

Tesf.ingperSpecification4.4.6.2.2dnotrequired.

SEABROOK - UNIT 1 3/4 4-24

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III. R'etype of Proposed Chances See attached retype of proposed changes to Technical Specifications. The attached retype reflects the currently issued version of Technical Specifications. Pending Technical Specification changes or Technical Specification changes issued subsequent to this submittal are not reflected in the enclosed retype. The enclosed retype should be checked for continuity with Technical Specifications prior to issuance.

l Revision Lars are provided in the right hand margin to designate a change in the text.

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" REACTOR COOLANT SYSTEM l

REACTOR COOLANT SYSTEM LEAKAGE l

OPERATIONAL LEAKAGE ,

LIMITING CONDITION FOR OPERATION l l

.3.4.6.2 Reactor Coolant System leakage shall be limited to: ;

a. No PRESSURE BOUNDARY LEAKAGE. ,

b. 1 gpm UNIDENTIFIED LEAKAGE.

c. 1 gpm total reactor-to-secondary leakage through all steam generators !

and 500 gallons per day through any one steam generator. ;

d. 10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System. ,

e. 40 gpm CONTROLLED LEAKAGE at a Reactor Coolant System pressure of l 2235 psig 20 psig. and j

f. 0.5 gpm leakage per nominal inch of valve size up to a maximum _of 5 gpm at a Reactor Coolant System pressure of 2235 20 psig from any Reactor Coolant System Pressure Isolation Valve.* ,

APPLICABILITY: MODES 1. 2. 3. and 4. j ACIl@: l

a. With any PRESSURE B0UNDARY LEAKAGE. be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . ;

b. With any Reactor Coolant System leakage greater than any one of'the !

above limits, excluding PRESSURE BOUNDARY LEAKAGE and leakage from <

Reactor Coolant System Pressure Isolation Valves, reduce the leakage i rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT STANDB) i within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 i hours.

c. With any Reactor Coolant System Pressure Isolation Valve leakage i greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by l use of at least two closed manual or deactivated automatic valves, or !

be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD !

SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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Test pressures less than 2235 psig but greater than 150 psig are allowed. t Observed leakage shall be adjusted-for the actual test pressure up to !

2235 psig assuming the leakage to be directly proportional to pressure dif- l ferential to the one-half power. !

SEABROOK - UNIT 1 3/4 4-21 Amendment No. l

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REACTOR COOLANT SYSTEM i

REACTOR C001. ANT SYSTEM LEAKAGE OPERATIONAL LEAKAGE i

SURVEILLANCE REQUIREMENTS 4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve shall be demonstrated OPERABLE by verifying leakage to be within its limit:

a. At least once per 18 months,

b. Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 7 days or more and if leakage testing has not been performed in the previous 9 months,

c. Prior to returning the valve to service following maintenance, repair, or replacement work on the valve. and !

d. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual ;

action or flow through the valve,

e. As outlined in the ASME Code,Section XI, paragraph IWV-3427(b). :

The provisions of Specification 4.0.4 are not applicable for entry into MODE ;

3 or 4.

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SEABROOK - UNIT 1 3/4 4-23 Amendment No. 30,-

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SEABROOK - UNIT 1 3/4 4-24 Amendment No.

i IV. Ifetermination of Sinnificant Hazards for License Amendment Request 95-03 Proposed '

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Channes ,

The proposed changes have been evaluated against the standards in 10 CFR 50.92 and have been detennined to not involve a significant hazards consideration, in that operation of the facility in accordance with the proposed amendment:

l. Would not involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed relocation of Technical Specification Table 3.4-1 does not alter the requirements

for pressure isolation valve operability currently in the Technical Specifications. The probability i of occurrence of a previously evaluated accident is not increased because this change does not #

introduce any new potential accident initiating conditions. The consequences of accidents previously evaluated in the UFSAR are not affected because the ability of the PlVs to limit !

leakage through these valves in amounts that do not compromise safety is not affected. Therefore, the proposed change does not involve a significant increase in the probability or consequences of i an accident previously evaluated.

2. Would not create the possibility of a new or di[ferent type of accident from any accident previously evaluated.

I All PlVs will continue to be tested to the same rigorous requirements as defined in the Technical Specification Surveillance Requirements. The proposed change does not make changes to the ;

plant or in the method that any safety related system is tested or performs its safety function.

Therefore, the possibility of an accident of a different type than any previously evaluated in the UFSAR is not created.

3. Would not involve a sigmficant reduction in a margin ofsafety. [

The administrative change to relocate Technical Specification Table 3.4-1 to the Technical Requirements Manual does not alter the basic regulatory requirement for RCS pressure isolation !

and will not affect the isolation capability for credible accident scenarios. Future revisions to the Technical Requirement Table will be subject to evaluation pursuant to 10CFR50.59. ;

'i The proposed relocation of Technical Specification Table 3.4-1 does not alter the requirements for pressure isolation valve operability currently in the Technical Specifications. The LCO and l Surveillance Requirements would be retained in the revised Technical Specifications. Therefore, the proposed change will not affect the meaning, application, and function of the current Technical Specification requirements for the valves in Table 3.4-1. Therefore, the proposed changes do not result in a significant reduction in the margin of safety. ;

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V.. Noosed Schedule for License Amendment Issuance and Effectiveness ,

I North Atlantic requests NRC review of License Amendment Request 95-03 and issuance of a

! license amendment having immediate effectiveness by November 24,1995, Nonh Atlantic is !

scheduled to begin the founh refueling outage in November 1995. ,

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4 VI. I'nvironmental Impact Assessment North Atlantic has reviewed the proposed license amendment against the criteria of 10CFR51.22 for environmental considerations. The proposed changes do not involve a significant hazards consideration, nor increase the types and amounts of efiluent's that may be released offsite, nor significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, North Atlantic concludes that the proposed change meets the criteria delineated in 10CFR51.22(c)(9) for a categorical exclusion from the requirements for an Environmental Impact Statement.

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ML20086R211

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