Text

Amend 62 to License DPR-3,revising Tech Specs to Clarify Term Operable as Applied to Single Failure Criterion for Power Reactor Safety Sys
	ML19341B040
Person / Time
Site:	Yankee Rowe
Issue date:	01/12/1981
From:	Crutchfield D; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML19341B036	List: ML19341B035; ML19341B040; ML19341B042; ML19341B046;
References
	NUDOCS 8101300082
	Download: ML19341B040 (14)
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UNITED STATES NUCLEAR REGULATORY COMMISSION y,

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%,.....f YANKEE ATOMIC ELECTRIC COMPANY DOCKET N0. 50-29 YANKEE NUCLEAR POWER STATION (YANKEE-ROWE)

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 62 License No. DPR-3 1.

Th Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Yankee Atomic Electric Company (the licensee) dated May 20,1980, (Proposed Change No. 169), complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission;

. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security 'or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's. regulations and all applicable requirements. have been satisfied.

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2.

Accordingly, the license is amended by changes to the Technical a

Specifications as indicated in the attachment to this license j

amendment and paragraph 2.C(2) of Facility Operating License i

No. DPR-3 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 62, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION h.

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Dennis M. Crutc ifTsid, CMef '

Operating Reactors Branch #5 Division of Licensing l'

Attachment:

Changes to the Technical Specifications JAN 121961 Datt of Issuance:

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ATTACHMENT TO LICENSE AMENDMENT NO. 62 FACILITY OPERATING LICENSE NO. DPR-3 DOCKET NO. 50-29 Revise Appendix A Technical Spec fications 'y removing the pages i

identified below and inserting the enclcsed pages.

The revised pages include the captioned amendment number and contain vertical lines indicating the areas of changes.

Remove Insert V - VI V* - VI 3/4 0-1 -- 3/4 0-0 3/4 0-1 -- 3/4 0-2 3/4 7-9 -- 3/4 7-10 3/4 7-9* -- 3/4 7-10 B3/4 0-1 -- B3/4 0-2 B3/4 0-l** -- B3/4-0-2 83/4 0-2A B3/4 7-3 -- B3/4 7-4 B3/4 7-3 -- B3/4 7-4*

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These pages are only included to correct the amendment numbers appearing at the bottom of the overleaf pages issued by License Amendment No. 61, dated 7/21/80.

- 0verleaf page; no changes involved.

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION PAGE MAIN COOLANT ** SYSTEM (Continued) 3/4.4.6-CHEMISTRY..............................................

3/4 4-12 3/4.4.7 SPECIFIC ACTIVITY......................................

3/4 4-15 i

3/4.4.8 PRESSURE / TEMPERATURE LIMITS Main Coolant System....................................

3/4 4-19 Pressurizer........................................<...

3/4 4-25 3/4.4.9

. STRUCTURAL INTEGRITY...................................

3/4 4-26 3/4.4.10 STEAM GENERATORS.......................................

3/4 4-32 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATOR............................................

3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS........................................

3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS........................................

3/4 5-9 3/4.5.4 SAFETY INJECTION TANK..................................

3/4 5-12 l 3/4.6 CONTAINMENT SYSTEMS l

3/4.6.1 PRIMARY CONTAINMENT l

Containment Integrity..................................

3/4 6-1 Containment Leakage....................................

3/4 6-2 Containment' Air Lock...................................

3/4 6-4 Internal Pressure......................................

3/4 6-5 A i r T em p e ra tu re........................................

3/4 6-6 Containment Vessel Structural Integrity.................

3/4 6-7 i

l Continuous Leak Monitoring System......................

3/4 6-8 1

3/4.6.2 CONTAINMENT ISOLATION VALVES...........................

3/4 6-9 l

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L YANKEE-ROWE y

Amendment No. 46, 54,59-l 9/14/,79-

INDEX QMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUI PAGE SECTION 3/4.6.3 COMBUSTIBLE GAS CONTROL 3/4 6-16 Hydrogen Analyzer......................................

3/4 6-17 Hydrogen Vent System...................................

3/4 6-18 Atmosphere Recirculation System........................

3/4.7 PLANT SYSTEMS 3/4.7.1 T'JRBINE CfCLE 3/4 7-1 Safety Valves..........................................

3/4 7-5 Emergency Boiler Feedwater System......................

3/4 7-6 Primary and Demineralized Water Storage Tanks..........

3/47-7 Activity...............................................

Turbine Generator Throttle and Control Valves..........

3/4 7_-9 l

STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION........

3/4 7-13 3/4.7.2 3/4.7.3 PRIMARY PUMP SEAL HATES SYSTEM (Deleted)...............

3/4 7-14 2

3/4 7-16 I

3/4.7.4 SERVICE WATER SYSTEM (Deleted).........................

l 3/4.7.5 CONTROL ROOM VENTILATION SYSTEM EMERGENCY SHUTDOWil.....

3/4 7-18--

3/4 7-19 3/4.7.6 SEALED SOURCE CONTAMINATION............................

3/4.7.7 YASTE EFFLUENTS 3/4 7-21 Radioactive Solid Waste................................

-3/4 7-22 Radioactive Liquid Waste...............................

Radioactive Gaseous Waste..............................-

-3/4 7_-23 3/4.7-24 3/4.7.8 ENV IRONMENT AL MON ITORI NG...............................

3/4.7-27' l

3/4.7.9 ~ SHOCK SUP PRESSORS (SNUBBEF 3 )..........................

3/4 7-30 3/4 7.10' FIRE SUPPRESS 10ff SYSTEMS...............................

3/4 7.11 P ENETRATIOM F IRE. BARRI ERS...............................

3/4 7-37 YANKEE-ROWE VI.

Amendment f!o. 47, 52, 5f i 61 9/14/79 l

13/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY LLIMITING CONDITION FOR OPERATION l

3.0.1 Limiting Conditions for Operation and ACTION requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for each specification.

3.0.2 Adherence to the requirements of the Limiting Condition for f%)eration and/or associated ACTION within the specified time interval

]'shall constitute compliance with the specification.

In the event the Limiting Condition for Operation is restored prior to expiration of the

!specified time interval, completion of the ACTION statenent is not required.

303 In the event a Limiting Condition for Operation and/or associated ACTION requirements cannot be satisfied because of circumstances in excess of those addressed in the specification, the facility shall be

'placed in at least ROT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months unless corrective measures are completed that permit operation under the permissible ACTION statements for the specified time interval as measured from initial discovery, or until the reactor is placed in a MODE in which the specifiertion is not applicable. Exceptions to these requirements shall be stated in the lindividual specifications.

I 13 0.4 Entry into an OPERATIONAL MODE or other specified applicability

' condition shall not be made unless the conditions of the Limiting Condition for Operation are met without reliance on provisions contained j

in the ACTION statements unless otherwise excepted. This provision shall Inot prevent passage through OPERATIONAL MODRS as required to comply with (ACTION statements.

3 0.9 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power scarce is OPERABLE: and (2) all of its redundant system (s). subsystem (s), train (s), component (s) and device (s) are OPERABLE, or likewise satisfy the requirements of this specification. Unless both conditions (1) and (2) are satisfied, the unit shall be placed in at least ROT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and in at least COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . This specification is not applicable in MODES 5 or 6.

lYANKEE-ROWE 3/4 0-1 Amendment No. 62

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3/4.0 APPLICABILITY 1

SURVEILLANCE REQUIREMENTS T

4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the i

specified time interval with:

a.

A maximum allowable extension not to exceed 25 percent of the surveillance intervsll and 4

F b.

A total maximum combit.ed interval time for any 3 consecutive surveillance intervals not to exceed 3 25 times the specified i

1 surveillance interval.

4.0.3 Performance of a Surveillance Requirement within the specified r

time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ~ ACTION statements unless otherwise required by the specification.

4.0.4 Entry into an OPERATIONAL MODE or other specified applicability condition shall not be made unless the. Surveillance Requirement (s) 1 associated with the Limiting Condition for Operation have been performed within the stated surveillance interval.or as otherwise specified. -

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3/4 0-2.

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Amendment No. 62 t

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4 PLANT SYSTEMS.

TUR8INE GENERATOR THROTTLE AND CONTROL VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each turbine generator throttle and control valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

MODES 1 - With one turbine generator throttle or control valve inoperable.

POWER OPERATION may continue provided the inoperable valve is either restored to OPERABLE status or closed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; Otherwise, be in at least HOT SHUTDOWN within the next 12 l

hours.

MODES 2 - With one turbine generator throttle or control valve inoperable, and 3 subsequent operation in MODES 1, 2 or 3 may proceed provided the inoperable valve is maintained closed; otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The provisions of Specification 3.0.4 are not applicable.

I SURVEILLANCE REQUIREMENTS 4.7.1.5 Each turbine generator throttle and control valve that is open shall be demonstrated OPERABLE by:

t Cycling each valve through at least one complete cycle of full a.

travel at least once per month, and b.

Verifying full closure within 2 seconds on any closure actuation signal whenever shutdown longer than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , if not performed in the previous 92 days.

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t YANKEE-R0WE 3/47-9 Amendment No. 49 5/30/78 e

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YANXEE-ROWE 3/4 7-10 knendment No. 61 l

3/4.0 APPLICABILIT_Y BASES The specifications of this section provide the general requirements npplicable to each of the Limiting Conditions for Operation and Surveil-iance Requirements within Section 3/4.

3.0.1 This specification defines the applicability of each spect-fication in terms of defined OPERATIONAL MODES or other specified conditions and is provided to delineate specifically when each specific-ation is applicable.

3.0.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual _ Limiting Condition for Operation and associated ACTION requirement.

3.0.3 This specification delineates the ACTION to be taken for circumstances not directly provided for in the ACTION statements and For whose occurrence would violate the intent of the specification.

example, Specification 3.1.2.-6 calls for two charging pumps to be OPERABLE and provide: explicit ACTTON requirements when only one

'Jnder the terms of Specification 3.0.3, if charging pump is OPERABLE.

no charging pumps are OPERABLE, i.hc facility is required to be in at least H0T STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and in COLD SHUTDOWN within the fol ing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

f This specification provides that entry into an OPERATIONAL 3.0.4 MODE or other specified applicability condition must be made with (a) l the full complement of required systems, equipment or components OPER-l ABLE and (b) all other parameters as specified in the Limiting Conditions for Operation being met without regard for allowable deviations and out of service provisions contailed in the ACTION statements.

The intent of this provision is to insure that facility operation is not initiated with either required equipment or systems inoperable or other specified limits being exceeded.

Exceptions to this provision have been provided for a limited number of specifications when startup with inoperable equipment would I

These exceptions are stated in the ACTION not affect plant safety.

statements of the appropriate specifications.

YANKEE-ROWE B 3/4 0-1 Amendment No. 58 4/3/79

BASES 3 0.5 This specification delineates what anditional conditions must be satisfied to perrit operation to continua acnsistent with the ACTION statements for power sources, when a normal cr emergency power source is not OPERABLE.

It specifically prohibits operation when ene divisien is inoperable because its normal or emergency power source is inoperable and a system, subsyste=, train, component er device in another division is inoperable fer another reason.

The provisions of this specification permit the ACT:CN statements associated with individual systems, subsystems, trains, components, or devices to be censistent with the ACTION statements of the associated electrical power source.

It allows operation to be governed by the time limits of the ACTION state =ent associated with the Limiting Condition for Operation for the normal or emergency power source, not the individual ACTION state =ents for each system, subsyste=, train, co:ponent or device that is determined to be inoperable soley because of the inoperability of its normal or e:ergency power source.

For exa:ple, Specification 3.8.1.1 requires in part that three e=ergency diesel generators be OPERABLE. The ACTION statement provides for a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months out-of-service time when ene emergency diesel generator is not OPER ABLE.

If the definition of OPERABLE were applied without consideration of Specification 3 0.5, all syste=s, subsyste=s, trains, components and devices supplied by the inoperable emergency power source would also be inoperable. This would dictate invoking the applicable ACTION statements for each of the applicable Limiting Conditions for Operation.

However, the provisions of Specification 3 0.3 permit the time li=its for continued operation to be consistent with the ACTION statement for the inoperable emergency diesel generator instead, provided the other specified conditions are satisfied. In this case this would mean that the vorresponding normal power source must be OPERABLE, and all recundant systems subsystems, trains components and devices must be OPERABLE, or otherwise satisfy Specification 3 0.5 (i.e., de capable of performing their design function and have at least one normal er one emergency power source OPERABLE).

If they are not satisfied, shutdown is required in accordance with this specification.

In MODES 5 or 6 Specification 3 0.5 is not applicable, and thus the individual ACTION statements for each applicable Limiting Condition for i

Operation in these MODES cust be adhered to.

YAKKEE-ROWE B 3/4 0-2 Amendment No. 62

APPLICABILITY BASES 4.G.1 This specification provides that surveillance activities necessary to insure the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL MODES or other conditions for which the Limiting Conditions for Operation are applicable. Provisions for additional surveillance activities to be performed without regard to the applicable OPERATIONAL MODES or other conditions are provided in the individual Surveillance Requirements.

4.0.2 The provisions of this specification provide allowable tolerances for performing surveillance activities beyond those specified in the nominal surveillance interval. These tolerances are necessary to provide operational flexibility because of scheduling and performance considerations.

The tolerance values, taken either individually or consecutively over 3 test intervals, are sufficiently restrictive to ensure that the reliability associated with the surveillance activitiy is not significantly degraded beyond that obtained from the nominal specified interval.

4.0.3 The provisions of this specification set forth the criteria for determination of compliance with the OPERABILITY requirements of the Limiting Conditions for Operation. Under this criteria,. equipment, systems or components are assumed to be OPERABLE if the asacciated surveillance activities have been satisfactorily performed within the specified time interval. Nothing in this provision is to be-construed as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the -Surveillance j

Requirements.

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4.0.4 This specification ensures that the surveillance activities associated with a Limiting Condition for. Operation have been performed '

within the specified time interval prior.to entry into. int OPERATIONAL MODE or other applicable condition..Thesintent of.this provision is to

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ensure that surveillance-activities have been satisfactorily demonstrated l

on a current basis as required to meet the OPERABILITY requirements of l

the Limiting Condition for Operation.

I Under the terms of this specification, for example, during-initial plant :

startup or following extended plant outages, the applicable -surveillance activities must be performed within the stated surveillance intervalt prior to placing or returning the system or' equipment into OPERABLE q

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YANKEE-ROWE.*

B 3/4 0-2A Amendment No. 62 i

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l PLANT SYSTEMS 1

BASES I

3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that' the resultant off-site radiation dose will be limited to a small fraction r

of 10 CFR Part 100.imits in the event of a steam line rupture.

This I

dose also includes the effects of a coincident 1.0 GPM primary to sec-i ondary tube leak in the steam generator of the affected steam.line.

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These values are consistent with the assumptions used in the accident F

analyses.

The steam break accident is based upon a postulated release of the

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entire contents of the secondary system to the atmosphere using a site boundary dose limit of 1.31 rem for thyroid dose.

O The limiting dose for this accident results from iodine in the I

secondary coolant. The reactor distribution of iodine isotopes with li failed fuel was used for this calculation.

1-131 is the dominant iso-tape because of its low MPC in air and because the other iodine isotopes have shorter half-lives and therefore cannot build up to significant concentrations in the secondary coolant, given the limitations on primarysystemleakrateangactivity. The entire secondary system

'j contains approximately 132m of water at standard conditions. One-tenth of the contained iodine is assumed to reach the site boundary, making allowance for plate-out and retention in water droplets.

3/4.7.1.5 TURBINE GENERATOR THROTTLE AND CONTROL VALVES The OPERABILITY of the turbine generator throttle and control valvesensuresthateachsteamgeneratorwillbeiso}atedattheinstant of scram for a LOCA with an area. sm.siler than 0.1 f t, as assumed in the accident analysis. The OPERABILITY of the turbine generator throttle and control valves within the closure times of the surveillance require-ments is consistent with the assumptittt *ised in the accident analyses.

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YANKEE-ROWE B 3/4 7-3 Amendme'nt (fo. 61

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PLANT SYSTEMS BASES 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations are based on a steam generator initial RT lP us 60'F and are sufficient NDT to prevent brittle fracture.

3/4.7.3 PRIMARY PUMP SEAL WATER SYSTEM (Del eted) 3/4.7.4 SERVICE WATER SYSTEM (Deleted) 3/4.7.5 CONTROL ROOM VENTILATION SYSTEM EMERGENCY SHUTDOWN The OPERABILITY of the control room ventilation system emergency shutdown enhances the opportunity for the control room to remain habitable for operations personnel during and following accident conditions.

3/4.7.6 SEALED SOURCE CONTAMINATION The limitations on sealed source removable contamination ensure that the total body or individual organ irradiation does not exceed allowable limits in the event of ingestion or inhalation of the source material. The limitations on removable contamination for sources re-quiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. Leakage of sources excluded from the requirements of this specification represent less than one maximum permissible body burden for total body irradiation if the source mat-erial is inhaled or ingested.

P YANKEE-ROWE B 3/4 7-4

- Amendment No. 52 11/14/78

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ML19341B040

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