Text

Amend 167 to License DPR-61,changing Plant TS to Allow Redundant Train Operability to Be Verified Operable by Exam of Appropriate Plant Records Rather than Performing Test of Redundant Equipment
	ML20057E200
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	10/04/1993
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	;
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ML20057E197	List: ML20057E196; ML20057E200; ML20057E201;
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	NUDOCS 9310080096
	Download: ML20057E200 (11)
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E UNITED STATES

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NUCLEAR REGULATORY COMMISSION g..v,/

WASHINGTON, D.C. 20555-0001 i

CONNECTICUT YANKEE ATOMIC POWER COMPANY 1

DOCKET NO. 50-213 l

HADDAM NECK PLANT' AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No.

167 License No. DPR-61 1.

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

j A.

The application for amendment by Connecticut Yankee Atomic Power Company (the licensee), dated July 26, 1993, complies with the i

standards and requirements of the Atomic Energy Act of 1954, as l

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; C.

There is reasonable assurance'(1) 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 i

conducted in compliance with the Commission's regulations;-

D.

The issuance of this amendment will not be inimical to the comon-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 Commission's regulations and all applicable requirements have been satisfied.

i 9310000096 931004 PDR ADOCK 05000213 j'

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2-I 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, 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.167, are hereby. incorporated in the license.

The licensee shall operate the facility in accordance with the -

Technical Specifications.

i 3.

This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance..

FOR THE NUCLEAR REGULATORY COMISSION 1

John F. Sto z, Director Project Directorate I-4 Division of Reactor Projects - I/tI~

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

October 4,1993 l

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ATTACHMENT TO LICENSE AMENDMENT NO.167 -

FACILITY OPERATING LICENSE NO.= DPR-61' t

DOCKET NO. 50-213-l Replace the following page of the Appendix A Technical Specifications with the

-i enclosed page. The revised page is identified by amendment number and contains vertical lines indicating the areas of change.

J Remove

-Insert i

3/4 5 3/4 5-1 3/4 5-2 3/4 5 3/4 5-3 3/4 5-3'-

3/4 5-4 3/4 5-4 e

3/4 5-5 3/4 5-5 3/4 5-8 3/4 5 B3/4 5-1 B3/4 5-1_-

B3/4 5-la 4

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3/4.5 EMERGENCY CORE COOLING SYSTEMS-t f

O 3/4.5.1 ECCS SUBSYSTEMS - Tavo GREATER THAN OR E00AL TO 350*F 3

k j

LIMITING CONDITION FOR OPERATION 3.5.la shall be OPERABLE with each subsystem comprised.of:Two in

)

1.

One OPERABLE centrifugal charging pump,.

2.

i One OPERABLE High Pressure Safety Injection pump, t

i 3.

i l.

One OPERABLE Low Pressure Safety Injection pump, 4.

Onc OPERABLE RHR heat exchanger, 5.

One OPERABLE RHR pump, and 6.

An OPERABLE flow path capable of taking suction fromLthe r' fueling water storage tank on a Safety-Injection signal' and manually e

transferring suction to the containment sump during the l

recirculation phase of operation, b.

The flow path _ from the reactor cavity to the containment sump,.

which consists of.four open reactor cavity pool seal hatches andi open transfer canal drain. valves shall-be OPERABLE..

APPLICABILITY:. MODES 1, 2, and 3.

ACTION:

With one ECCS subsystem inoperable, verify OPERABILITY of the

.a.

remaining High. Pressure Safety Injection pump, Low Pressure Safety Injection pump, or the RHR pump within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or beLin 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 HOT the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With the flow path from the' reactor cavity to the containment sump-inoperable, restore the flow path to OPERABLE status within one.

hour or be in HOT STANDBY within the next.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in C SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

In the event the ECCS is actuated'and' injects water trito the -

c.

Reactor Coolant System, a Special Report shall be prepared 'and

. submitted to the Commission pursuant-to Specification 6.9.2 within

90. days describing the' circumstances.of the actuation'and the.

total accumulated-actuation cycles to date.

The current value'of 1

the usage' factor for each affected Safety Injectioninozzle shall be provided in-this Special-Report whenever its.value exceeds.

0.70.

HADDAM NECK-9174 3/4 5-1 Amendment No.' JJJ,167) l

EMERGENCY CORE COOLING SYSTEMS'

=

SURVEILLANCE REQUIREMENTS l

4.5.1 Each ECCS subsystem shall be demonstrated OPERABLE:

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the following valves a.

are in the indicated conditions:

Valve Number Valve Function Valve Position i

RH-FCV-602 RHR Heat Exchanger ~ Blocked closed. Operator air Bypass Line supply isolated.

RHR Heat Exchanger Blocked open position.

RH-FCV-796 Discharge Line Operator-air supply isolated.

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RH-MOV-22 Containment Sump-Closed. Manual Operator is i

Suction Line locked.-

SI-MOV-24 RWST Line Locked open. Operator circuit-breaker locked open.

4 RH-MOV-874 RHR Recirculation Locked closed. Operator Line.

circuit breaker locked open.

i SI-MOV-854A HPSI Pump Open. Manual Operator is Suction Line locked.

SI-MOV-854B HPSI Pump Open. Manual Operator is Suction Line locked.

SI-MOV-901 RHR/HPSI Crosstie Closed. Manual-Operator is i

locked.

SI-MOV-902 RHR/HPSI Crosstie-Closed. Manual Operator is locked.

SI-MOV-903 HPSI Miniflow Open. Manual operator is locked.

SI-MOV-904 HPSI Miniflow Open. Manual Operator is i

locked.

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-HADDAM NECK 0174 3/4 5-2 Amendment No. Jg 167 1

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) b.

At least once per 31 days by:

g i

Verifying that each valve (manual, power-operated or 1) automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

i Verifying that each of.the following pumps develops greater 2) i than or equal to the indicated discharge head pressure and differential pressure on recirculation flow when tested i

pursuant to Sections 4.0.5.

Discharge Head Differential Pressure Pressure a)

High Pressure Safety A

1392 psig i 1374 psid Injection Pump B

1392 psig 1 1374 psid b)

Low Pressure Safety A

322 psig 1 304 psid Injection Pump B

322 psig 1 304 psid c)

Residual Heat Removal A

145 psig 1 112 psid i

Pump B

145 psig 1 112. psid 3)

Verifying the hydraulic characteristics of the centrifugal l

charging pumps (A and B) pursuant to Section 4.0.5.

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4)

Verifying that containment sump suction valve RH-MOV-22 can be cycled manually from the control room and valve RH-V-808A can be manually cycled locally.

By a visual inspection which verifies that no loose debris (rags,

.i c.

trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. The'. visual inspection shall be performed:

1)

Of all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY. This includes verifying all reactor cavity pool seal hatches are open, gratings installed, and also that the transfer canal drain valves WD-V-203 and WD-V-970 are open, and i

HADDAM NECK 3/4 5-3 Amendment No. JU 167 aus

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2)

Of-the areas within containment. affected by the work: activity within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months following each containment Lentry,- except for-entries made only for surveillance. or-inspection, when CONTAINMENT.

' I INTEGRITY is established... In:the event of multiple containment entries,. an -inspection shall be performed' atrienst once every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Inspection' required by this. paragraph shall-be performed :

prior to the containment' air lock testing.

d.

At least once per 18 months by:.

Verifying.;that.when the. RCSE pressure (simulated.'oriactual) 1)-

increases above-400 psig, l proper 11nterlock iaction occurs 'to.

protect the RHR; System from being overpressurized by_the RCS.,

2)

A. visual inspection 5 of;. the containment sumpi and verifying that the. drain ' trenches and cover gratings are not: restricted.

by debris and show, no evidence of ' structural distress.or; abnormal corrosion.

e.

At least once. per 18 months, during ' shutdown,-' by:1

.l 1)

Verifying.that each automatic 'and ~ manual ivalve shown ~ on -- Table -

'4.5-1 in the flow path actuates-to' its correct position 'on a safety. injection actuation test: signal..

2)

Verifying that' each remote' valve, -shown on Table-4.5-2 in the ECCS flow path Hcan be = cycled by. manual: action.from; the control ~ rnom.

3)

Verifying that

.each of the

-following~ pumps

. start' automatically, upon _ receipt -of.aSafetyi Injection. Actuation.

test' signal:-

a)

High-Pressure Safety Injection pump,-and b)

Low Pressure Safety; Injection pump.

4)

Performance 1of a1 CHANNEL CALIBRATION of. theJ charging flow

~

transmitter.

f.

At least ' once per I'8 months, ~ during '. shutdown, ' the remotely -

controlled, motor-operated containment spray? water valve sha111be operated under a "no-flow" condition. ;The test = will-- be ' considered '

satisfactory.if hvisual observation shows thati the valve nas

~

operated satisfactorily.

HADDAN NECK 3/4 5-4

' Amendment No. JU. JA7,1671 0174

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1 EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)

Periodic leakage testing of each ~ ECCS. check valves, SI-CV-862A, l

g.

SI-CV-862B, SI-CV-862C, SI-CV-862D, SI-CV-872A, and SI-CV-872B shall be accomplished prior to entering MODE 1 operation:

1)

After every time the plant 'is placed in the cold shutdown 1

condition for refueling.

2)

After every time the plant has been placed in the cold shutdown condition for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months if L testing has not been accomplished in the preceding 9 months.

3)

Prior to returning.the valve to service after maintenance, repair, or replacement work is performed.

Leakage may be measured indirectly. using pressure indicators, if accomplished in accordance with approved procedures. and supported by computations showing that the method is capable of-demonstrating compliance with the-leakage criteria of Section 3.4.6.2.

The minimum differential pressure across. these check valves during these leakage tests shall_ not be less than 150 psid.

h.

The correct position of each ECCS throttle valve listed below shall l

be verified within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following completion of each valve stroking operation or maintenance on the valve ~ when the ECCS subsystems are required to be OPERABLE.

ECCS Throttle Valves Valve Number SI-V-905 SI-V-906 SI-V-907 SI-V-908 1.

A flow balance test shall be performed, during Mode 5 or 6, following completion of modifications to the ECCS subsystems that j

alter the subsystem flow characteristics, to verify that for the High Pressure Safety Injection pump injection lines, with a single pump running and two lines isolated, the flow rate through each -

unisolated line is equal to 1000 i 100 gpm.

HADDAM NECK 3/4 5-5 Amendment No. JU,167 0174

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EMERGENCY CORE COOLING SYSTE:iS r

SURVEILLANCE RE0VIREMENTS

)

4.5.2 a.

The ECCS subsystems shall be demonstrated-OPERABLE per.L the applicable Surveillance Requirements of Specification' 3.5.1 with the. exception

that, for valves - - RH-FCV-602 -- and RH-FCV-796, restoration of. valve controls be ' allowed.-

l b.

One centrifh;;al charging. pump and' both High Pressure Safety i

Injection pumpr shall ~ be demonstrated. : inoperable..at least l

once per 31 days whenever the temperature of one-or more.of the RCg cold' lags of an unisolated loop is less than or equal to 315 F and-the.'RCS is not vented-by a minimum opening of 3' inches (nominal' diameter) or its equivalent by verifying:-

l 1)

That the High Pressure Safety Injection. pump motor circuit breakers are racked out and the cabinets locked, 2)

That -High' Pressure Safety: Injection pump 1 discharge valves SI-V-855A and SI-V-855B are closed - and-locked,.

and 3)

That the inoperable centrifugal. charging pump's control switch is in the trip -pullout position and red tagged,

~"Do Not Operate."-

i Each ECCS subsystem'shall beidemonstrated'0PERABLE on start-up c.

prior to entering Mode _4:

VALVE NO.

LOCATION ACTION SI-V-905 HPSI Loop 1-

_ Valve blocked and locked Injection line in throttled position.

SI-V-906-HPSI' Loop 2 Valve blocked and locked Injection line-in throttled position.

SI-V-907 HPSI loop-3 Valve' blocked 'and locked Injection line in throttled position.

SI-V-908 HPSI loop 4 Valve blocked and locked l

Injection line in throttled position.

SI-MOV-873 Core deluge.line Locked open. Operator.

circuit breaker locked open.

j i

HADDAM NECK 3/4 5 Amendment No. JU,167 0175 I

J

7._

3/4.5 EMERGENCY CORE COOLING SYSTEMS lf i

q BASES

,i 3/4.5.1 and 3/4.5.2 ECCS SUBSYSTEMS The OPERABILITY of two independent ECCS subsystems ensures that sufficient emergency core cooling capability will be.available in the event of a LOCA 1

assuming the loss of one subsystem through-any single failure consideration.

j i

Either subsystem is capable'of supplying sufficient core cooling to limit the l

peak cladding temperatures within-acceptable limits for all postulated break -

sizes ranging from the double ended break of the-largest RCS cold leg pipe 1

downward. In-addition, each ECCS subsystem provides long-term core cooling capability in the recirculation mode during the accident recovery period.

j With the RCS temperature greater than or equal to 350'F 'and if one ECCS ~

^

l subsystem is inoperable, the other subsystem (i.e., HPSI, LPSI or.RHR) must be =

verified to be OPERABLE within two hours. :A verification of OPERABILITYiis an.

administrative check,;by examination of appropriate plant records -(e.g., logs--

and surveillance test records) to determine that the remaining ECCS subsystem' l

l 1s not inoperable.

i With the RCS_ temperature below 350*F, one OPERABLE ECCS subsystem is accept-able' without single failure consideration on the basis of the: stable reac-l In' tivity condition of the reactor-and the limited core cooling requirements.

1 Mode.4,-the RHR heat exchanger (s) may be. considered OPERABLE while aligned to the Component Cooling System.

The limitation for a maximum of one centrifuga1' charging pump:and one metering i

pump to be OPERABLE and the Surveillance. Requirement.to verify the remaining centrifugal charging pump and high pressure 1 safety injection pumps to be '

inoperable below 315'F provides. assurance that a mass addition pressure -

transient can be relieved by the operation of a single low temperature overpressurization relief valve.

In order to use the HPSI pumps to provide ~ high pressure recirculation follow-ing a small break loss of coolant accident (LOCA) _ coincident with a single active failure, the following modifications to the emergency core cooling:

system have been made. A piping crosstie between each HPSI pump suction and the RHR pump discharge has been installed.- LTwo valves, SI-MOV-901 and SI-MOV-902 have been installed in'this crosstie. The two manual HPSI' pump'.

l suction valves have been replaced with. motor-operated valves, SI-MOV-854A and

~

l.

B, to prevent contaminated water from entering the RWST when using(the HPSI pumps to provide flow to the core during recirculation..- Two MOVs' SI-MOV-903 l

and 904)~'in' series have been~ added to the HPSI:miniflowLline to provide-for.

redundant isolation of the:RWST during sump l recirculation.

The manual core deluge isolation valve-has been replaced with a de-energized motor-operated valve, SI-MOV-873..This valve is locked.open with-the breaker locked open to ensure:that adequate flow is available to the core l deluge system. The valve may be energized and closed if a core deluge valve-failed to close during transfer to sump. recirculation.

HADDAM NECK.

83/4'5-1.

Amendment No. p 167 :

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3/4.5 EMERGENCY CORE COOLING SYSTEMS BASES 3/4.5.1 and 3/4.5.2 ECCS SUBSYSTEMS (Continued)

The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that as a minimum, the assumptions used in.the' safety analyses are met -

and that subsystem OPERABILITY is maintained.

~

Surveillance requirements for throttle valve position and flow balance testing-provide assurance that proper ECCS flows will be maintained in the event of a l

LOCA.

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l HADDAM NECK B3/4.5-la

Amendme'nt' No. JJJ,167 etis

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ML20057E200

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