ML20247E678

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Amend 119 to License DPR-61,splitting & Revising Tech Spec Section 3.3.1.5 Re Isolated Loop
ML20247E678
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 07/18/1989
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20247E670 List:
References
NUDOCS 8907260256
Download: ML20247E678 (11)
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l- UNITED STATES t

8'  ? NUCLEAR REGULATORY COMMIS$10N

, a  ; - WASHINGTON, D. C. 20555

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I CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE

/mendment No. 119 License No. DPR-61

1. The' Nuclear Regulatory Connission (the Commission) has found thati j

A. The application for amendment by Connecticut Tankee Atomic Power (thelicensee),datedJanuary 10, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the consission's rules and regulations set forth l 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 Commission; C. There is reasonable assurance (i) that the activities authorized by I i

this amendment can be conducted without endangering the health and I safety of the public, and (ii) that such activities will be l cor. ducted in compliance with the Consission's regulations; i 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 I E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comrdssion's regulations and all applicable requirements have been satisfied, j

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l 8907260256 890718 PDR ADOCK 05000213 P PDC

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2. Accordingly, the license is amended by changes to the Technical -

Specifications as indicated in the attachment to this license amendment. f and paragraph 2.C.(2) of Facility Operating License No. DPR-61 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.119, 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 issuance, to be implemented within 30 days of issuance.

FOR THE NUCLEAR REG ATORY COMMISSION n F. Sto z, Direct r_ojpct Directorate Msion of Reactor Projects I/II Off?n of Nuclear Reactor Regulation Attachtent:

ChanDes to the Technical Specifications Date of Issuance: July 18, 1989 l

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ATTACHMENT TO LICENSE AMENDMENT NO.119 l

i FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Li.' Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 3-4f.1 3-4f 3-4f.2 3-4g 3-49 3-4h 3-4h.1 3-4h.2

. 3-41 3-41.1 3-41.2 3-4v 3-4v e

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i REACTOR COOLANT SYSTEM  !

ISOLATED LOOP LIMITING CONDITION FOR OPERATION i

- i 3.3.1.5 The RCS loop stop valves of an isolated loop

  • shall be shut and either:  !
a. The power removed from the valve operators, or )

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b. The boron concentration of the isolated loop shall be maintained greater than or equal to the boron concentration of the operating loops.

APPLICABILITY: MODES I and 2 ACTION _:

With the requirements of the above specification not satisfied, either:

a.

Remove power from the valve operators within one hour, or I b.

Increase the boron concentration of the isolated loop to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or c.

Be in at within theleast HOT 30 following STANDBY hours. within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in CDLD SHUTDOWN SURVEILLANCE RE0VIREMENTS i

a.

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, if required, verify that power is  !

removed from the valve operators,

b. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, if required, verify that the boron l concentration of an isolated loop is greater than or equal to the '

boron concentration of the operating loops.

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q A loop is considered to be isolated when the hot and cold leg stop valves )

are both closed.

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I Amendment No. 97, 119 l

3-4f.1 1 -

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REACTOR C03LANT SYSTEM-ISOLATED LOOP LIMITING CONDITION FOR OPERATION 3.'3.1.6 The RCS loop stop valves of an isolated loop

  • shall be shut and either:
a. The power removed from the valve operators, or
b. The boron concentration of the isolated loop shall be maintained greater than or equal to the boron concentration required to meet the SHUTDOWN MARGIN requirements of Specification 3.10.1.2 or 3.10.1.3 or the refueling boron concentration of Specification 3.13.

APPLICABILITY: MODES 3, 4, 5 and 6 ACTlQH:

With the requirements of the above specification not satisfied, either:

a. Remove power from the valve operators within one hour, or b.

Increase the boron concentration of the isolated loop to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or c.

Be in at within theleast HOT 24 following SHUTDOWN hours. within the next 6 hour: and in COLD SHUTDO SURVEILLANCE REQUIREMENTS' a.

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, if required, verify that power is removed from the valve operators,

b. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, if required, verify that the boron concentration of an isolated loop is greater than.or equal to the boron concentration required to meet the SHUTDOWN MARGIN requirements of Specification 3.10.1.2 or 3.10.1.3 or the refueling boron concentration of Specification 3.13.

A loop is considered to be isolated when the hot and cold leg stop valves are both closed.

1 3-4 f. 2 Amendment No. 97, 119

REACTOR COOLANT SYSTEM ISOLATED LOOP STARTUP LIMITING CONDITION FOR OPERATION bi3.1.7 A reactor coolant loop shall remain isolated until:

a.

The 200Ftemperature of at the cold leg of the isolated loop is within loop (s),.the highest cold deg temperature of the operating b.

The boron concentration of the isolated loops is greater than or equal to the boron concentration required to meet the SHUTDOWN MARGIN requirements of Specification 3.10.1.2. or 3.10.1.3 or the refueling boron concentration of Specification 3.13.

APPLICABILITY: MODES 3, 4, 5, and 6.

ACTION:

Withisolated the the requirements of the above specification not satisfied, do not open loop stop valves.

SURVEILLANCE REQUIREMENTS a.

Tne isolated loop cold leg temperature shall be determined to be within 200F of the highest cold leg temperature of the operating loops within 30 minutes prior to opening the cold leg stop valve.

b.

Within 30 minutes prior to opening the loop stop valves, the isolated loop shall be determined to have a boron concentration greater than or equal to the boron concentration required to meet the SHUTDOWN MARGIN requirements of Specification 3.10.1.2 or 3.10.1.3, or the refueling boron concentration of Specification 3.13.

An operating loop (s) may be a Reactor Coolant loop (s) or a Residual Heat Removalloop(s).

The above requirements do not apply when a hot leg stop valve is opened to create an idled loop.

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3-4g Amendment No. 97, 119 l

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REACTOR COOLANT SYSTEM

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IDLED LOOP LIMITING CONDITION FOR OPERATION l

333.1.8 The cold leg stop valve of an idled loop

  • shall be shut and either: 1 l
a. The power removed from the valve operator, or
b. The boron concentration of the idled loop shall be maintained greater than or equal to the boron concentration of the operating loops.

APPLICABILITY: MODES I and 2.

ACTION:

With the requirements of the above specification not satisfied, either:

a. Remove power from the valve operator within one hour, b.

Increase within the boron 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or concentration of the idled loop to within the limits c.

Be at at within theleast HOT30 following STANDBY hours. within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDO SURVEILLANCE REQUIREMENTS a.

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, if required, verify that power is I removed from the valve operators,

b. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, if required, verify that the boron concentration of an idled loop is greater than or equal to the boron '

concentration of the operating loops.

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  • i A loop is considered to be idled when the hot leg stop valve is open and the cold leg stop valve is closed.

l 3-4h.1 Amendment No. 97, 119

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REACTOR COOLANT SYSTEM )

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IDLED LOOP LIMITING CONDITION FOR OPERATION h.3.1.9 The cold leg loop stop valve of an idled loop

  • shall be shut and either:
a. The power removed from the valve operator, or b.

The boron concentration of the idled loop shall be maintained greater than or equal to the boron concentration required to meet the SHUTDOWN MARGIN requirements of Specification 3.10.1.2 or 3.10.1.3 or the refueling boron concentration Specification 3.13. o f.

APPLICABILITY: MODES 3, 4, S, and 6 i

ACTION:

With the requirements of the above specification not satisfied, either:

a. Remove power from the valve operator within one hour, b.

Increase within the boron 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or concentration of the idled loop to within the limits c.

Be in at within theleast HOT24 following SHUTDOWN hours. within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in' COLD SHUT SURVEILLANCE REQUIREMENTS a.

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, if required, verify that power is removed from the valve operators.

b. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, if required, verify that the boron  ;

concentration of an idled loop is greater than or equal to the boron '

concentration Specificationrequired to meet the SHUTDOWN MARGIN requirements of 3.10.1.2 or 3.10.1.3 or the refueling boron concentration of Specification 3.13.

A theloop coldis leg considered to be stop valve idled when the hot leg stop valve is open and is closed.

3-4h.2 Amendment No. 119 >

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REACTOR COOLANT SYSTEM IDLED LOOP STARTUP LIMITING CONDITION FOR OPERATIOff 3 3 .1.10 A reactor coolant loop shall remain idled until: 1

a. The temperature at the cold leg of the idled loop is within i 20'F loops, of the highest cold leg temperature of the operating '

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b. The boron concentration of the idled loop is greater than or equal to the boron concentration of the operating loops,
c. The reactor is no greater than 60% RATED THERMAL POWER.

APPLICABILITY: MODES I and 2.

ACTION:

With the requirements of the above specification not satisfied, do not open the idled loop cold leg stop valve.

SVRVEll. LANCE RE0VIREMENTS

a. Within 30 minutes prior to opening the idled stop valve, the idled loop cold leg temperature shall be determined to be within 200F of the highest cold leg temperature of the operating loops.
b. Within 30 minutes prior to opening the idled loop stop valve, the reactor shall be determined to be less than 60% RATED THERMAL POWER.

I c. Within 30 minutes prior to opening the loop stop valve, the idled loop shall be determined to have a boroa concentration greater than or equal to the boron concentration of the operating loops.

l 3-41.1 Amendment No. 119

REACTOR COOLANT SYSTEM E LED LOOP STARTUP LIMITING CONDITION FOR OPERATION 3 3 .1.11 A reactor coolant loop shall remain idled until:

a. The teniperature at the cold leg of the idled loop is within 208F of the highest cold leg temperature of the operating loop (s),
b. The boron concentration of the idled loops is greater than or equal to the boron concentration required to meet the SHUTDOWN MARGIN requirements of Specification 3.10.1.2 or 3.10.1.3 or-the refueling boron concentration of Specification 3.13.

APPLICABILITY: MODES 3, 4, 5, and 6 ACTION:

With the requirements of the above specification not satisfied, do not open the idled loop cold leg stop valve.

SURVEILLANCE RE0VIREMENTS

a. Within 30 minutes prior to opening the idled loop stop valve, the idled loop cold leg temperature shall be determined to be within 200F of the highest cold leg temperature of the operating loops.
b. Within 30 minutes prior to opening the idled loop stop valve, the boron concentration of the idled loop shall be determined to have a boron concentration greater than or equal to the boron concentration required to meet the SHUTDOWN MARGIN requirements of Specification 3.10.1.2 or 3.10.1.3, or the refueling boron concentration of Specification 3.13. If an idled loop is being restarted within 30 i i

minutes after a reactor trip, this surveillance requirement may be waived if the cold leg loop stop valve is closed for les's than 15 minutes.

An operating loop (s) may be a Reactor Coolant loop (s) or a Residual Heat Removal loop (s). ,

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3-41.2 Amendment No. 119

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.3.3.1 REACTOR COOLANT SYSTEN l

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3.2.1 itEACTOR COOLANT LOOPS AND COOLANT CIRCULATION fcontinuad.1 The operation of one Reactor Coolant Pump (RCP) or one RHR pump provides adequate flow to ensure mixing, prevent stratification and produce credual reactivity chan <

n the Reactor Coolant System. ges during baron concentration reductionsThe reactivity chanpe ra will, the forp, be within the capability of operator recognition and control. ,

The restrictions on starting an RCP.with one or more RCS cold legs les: than or equal to 315'F are provided to prevent RCS pressure transients, caused by which could exceed the energy additibnsGfrom limits of Appendix the Secondary to 10CFR Part 50. The Coolant RCS wiSystem,ll be protected against overpressure transients and will not exceed the limits of Appendix G by restricting starting of the RCPs to when the secondary water temperature of each steam generator is less than 20eF above each of the RCS cold leg tempera-tures.

Ths requirement to maintain the boron concentration of an isolated / idled loop l greater than or equal to the boron concentration of the operating loops or the boron concentration required to meet SHUTDOWN HARGIN requirements ensures that no unacceptable reactivit an isolated /id'od loop.y addition to the ,7 Verification corethe could occur boron during startup concentratica of in an isolated / idled loop prior to opening the sto; valves provides a reassurance of ine adequacy of the boron cencontration in the isolated / idle 1 cop. '

Startup of an isolated /icled loop could inject cool water from the loop into the core. The reactivity transient resulting from this cool water injectiec is minimized by prohibiting isolated is within 208F of the operating loops / idled loop startup until its temperature

. 2.2.2 SAEEI M LYES ,

The pressurizer Code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2735 psig. Each safety valve is designed to relieve 293 The relief capacity of,300 lbs. per hour of saturated steam at 2483 psig.a single overpressure condition which cculd occur during shutdown. In the event that no safety valves are OPERABLE, an opard.g RHR loop, connected to the RCS, provides overpressure relief capability red will prevent RCS overpressure-zaticn. In addition, the Overpressure Protection System provides a diverse means of protection gainst RCS overpressurization at low temperatures.

3 4v Amendment No. 119 L

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