ML20100B969

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Proposed Tech Specs Relocating Containment Isolation Valve List,Table 3.6-2 from TS to Technical Requirements Manual
ML20100B969
Person / Time
Site: Millstone Dominion icon.png
Issue date: 01/22/1996
From:
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20100B968 List:
References
NUDOCS 9601290338
Download: ML20100B969 (18)
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Docket No. 50-336 B15479 I

Attachment 3 l Millstone Nuclear Power Station, Unit No. 2 Proposed Technical Specifications Revision containment Isolation Valves i Marked-up Version of current Technical Specifications i

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January 1996 9601290338 960122 PDR ADOCK 05000336 p PDR

, h se-17 197 ,

DEFINITIONS .

ofere4ew ae. W dw 31 ]tinds (anD a5 % . 4 4 CONTAINMENT INTEGRITY m

't50t@tra+T*WA5 ad es "'t co w4 n l g% e Sbe. c aPAntd p i.f;c e a.d ,a.*

t. % y ,6.i.i or 1.8. C0NTAINMENT INTEGRITY shall exis
1. 8.1 All penetrations required to be closed during accident

. conditions are either: ..

a. Capable of being closed by an OPERABLE containment automatic isolation valve system, or = l
b. Closed by manual valves, blind flanges, or deactivated -

automatic valves secured in their closed positionsyy 1.8.2 The equipment hatch is closed and sealed, and 1.8.3 The airlock is OPERABLE pursuant to Specification 3.6.1.3.,

CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL '

CALIBRATION shall encompass the entire channel including the sensor and . <-

alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequen-tial, overlapping or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK .

1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This detemination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST 1.11 A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

e MILL 5 TONE - UNIT 2 1-2 l

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. 2n.6.i PRi m n CONTA2""E" c..wk.1, CONTAINMENT INTEGR m LIMITING CONb1T10N FOR OPERATION _

3.6.1.1 Primary CONTAINMENT INTE TY shall be maintained.

APPLICABILITY: MODES 1. 2. 3 an 4.

ACTION:

EGRITY* restore CONTAINMENT INTEGRITY within Without primary CONTAINMENT 1 STANDBY 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 one hour or be in at least 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SWTDOWN within the followi SURVE!LLANCE REQUIREMENTS 4.6.1.1 Primary CONTA! NT INTEGRITY shall be demonstrated:

t

a. At least o per 31 days by verifying that all penetratio capable of ng closed by CPERABLE containment automatic isota-tion valves nd required to be closed during accident conditions "

are closed by valves, blind flanges

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At least once per 31 days by verifying the equipment hatch is

b. I
  • closed and sealed.

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c. By verifyog the containment air lock is OPERABLE per Specifica-tion 3.6.1.3.
d. After each closing 'of a penetration subject to type 5 testing 7 (except the er a lett. bycontainment lank nie testing air lock)1the seal witha gas (64 at P. if enormd j

) and verifying that when the measured leakage rate for  ?

these seals is added to the leakage rate determined purstant '

to Specification 4.6.1.2.d for all other Type 5 and C penetra-ns the combined leakage rate is less than er equal l

K lN A CcoKDAHLg ww TNC conummeur tr$ggTr TW'"'s j 4peration within the time allowances of the ACTION statements of 3pecifica- I i tion 3.6.1.3 does not constitute a less of CONTAINMENT INTEGRITY.

N 3/4 6-1 d

MILLSTONE - UNIT 2 Amendment No. 25./

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  • Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, 'or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD S WTDOWN except that such verification need not be performed more often than once per 92' days.

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hmber7,19 CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION TOR OPERATION 3.6.3.1 The containment isolation valves \specified in Tabla 3.6-2[

shallbeOPERABLEXJig 'isolatib .44g s l +* N i 45 h}Eo1 AE r P'5* I"M M *Is .

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M6DESl,2,3and4.- ' '

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APPLICABILITY: '

ACTION: [

With one or more of the isolation valve (s) edinTable3.6-2) 6 inoperable, either:

a. Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or
b. Isolate the affected penetration (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of a )

deactivated automatic valve (s) secured in the isolation i

( position (s),or l

c. Isolate the affected penetration (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of a closed manual valve (s) or blind flange (s); or
d. Be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

SURVEILLANCE REOUIREMENTS Gack - o__ -

4.6.3.1.1 JKe isolation valve (specified in Table _3.6-2 aD testable during plant operation shall.b rJemonstrated OPERABLE:

a. At least once per 92 days by:
1. Exercising each power operatdd valve through one complete cycle of full travel and measuring the isolation time, and ,
2. Exercising each manual valve, except those that are closed, through one complete cy&1e of full travel.
b. Immediately prior to returning the valve to service after maintenance repair or replacement work is performed on the 6 i

MILLSTONE - UNIT 2 3/4 6-15

, . . . o. . . . . . . . , . . ..

4 .

rch 23,19[

CONTAINMENT SYSTEMS -

l SURVEILLANCE REQUIREMENTS (Continued) valve or its associated actuator, control or power circuit by performance of the applicable cycling test, above.

D 4.6.3.1.2 Each isolation valve @oecified in Table 3.6-2)sha11 be {

. demonstrated OPERABLE during.the, COLD SHUTDOWN or. REFUELING MODE at.. .

least once per 18 months by:- '

a. Verifying that on a containment isolation test signal, each isolation valve actuates to its isolation position,
b. Verifying that on a Containment Radiation-High signal, all containment purge valves actuate to their isolation position,
c. Exercising each power operated valve not testable during plan operation, through one complete cycle of full travel and l 20 measuring its isolation time, and
d. Exercising each manual valve not locked, sealed or otherwise '

secured in position th. rough at least one complete cycle of l 20 i full travel.

i MILLSTONE - UNIT 2 3/4 6-16

1_AULE 3.6_

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CONTAINMENT ISOLATION VALVES x TESTABLE DURING MLM V RVE NUMBER FUNCTION PtANT OPERATION IS ATION TIME .

A. CONTAI ENT ISOLATION VALVES 2-PMW-43 Primary Hakeup Water Yes 5 seconds 2-C11-089 Reactor Coolant letdown Line No 5 seconds 1 4

2-011-516 Reactor Coolant Letdown Line H 5 seconds p ,

2-SSP-16.1 Containment Sump to Aerated Waste 5' i; Orain Tank Yes 5 seconds j*

2-SSP-16.2 Containment Sump to Aerated Waste Drain Tank Yes 5 seconds g '

2-RC-001 ctor Coolant Sampilng Yes 5 seconds T 2-RC-002 Rea r Coolant Sampilng Yes 5 seconds [

G 2-RC-003 Reacto oolant Sampilng 1 Yes 5 seconds T 2-RC-45 Reactor C Reactor Cool ant Sampling Samp11

- ' Yes Yes 5 seconds 5 seconds 7

y 2-LRR-61.1 Steam Generator 5 seconds 2-MS-220A 2-MS-27.0R Steam Generator own Yes Yes 5 seconds j, 2-SI-312 Nitrogen Sup y Yes 5 seconds p i 2-lRR-43.1 Primary aln Tank to Clean Ra ste ,_f l' Sys Yes i 5 seconds, 2-LRR-43.2 Pr System ry Drain Tank to Clean Radwaste Yes i

5 seconds q {, '

2-C11-506 Reactor Coolant Pump Seal Controlled 4 Dicedoff . No 5 seconds 5Ei '

2-018-198 Reactor Conlant Pump Seal Controlled [{

Bleedoff No 5 seconds ~ >

2-C11-505 Reactor Coolant Pump Seal Controlled -

Bleedoff No seconds .;

2-GR-11 Waste Gas Ileader ,

Yes 5 sec ds 2-G 1.2 Waste Gas Ileader Yes 5 seconds  :

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TABLE 3 6-2 (Continued)

  • t CONTAllMIENT_ ISOLATION VALVES . ,

a2 s$

o VALVE MUMBER FUNCTION TESTABLE DURING PLANT OPERATION MAXIMUM _j ISOLATION TIME A

A. CONTAINMENT ISOLATION VALVES {

E C-12 Containment Air Sample Yes seconds , Il Containment Air Sample Yes 5 seconds P Z 2-A

% (il.

5 2-AC-2 Containment Air Sample Yes 5 seconds m

2-AC-47 Containment Air Sample Yes 5 seconds HV-8150- Containment f. r Sample Yes 5 seconds 7- ( ;

IIV-8151 Containment Air Sample Yes 5 seconds +-

M. t 2-MS-191A 2-MS-1918 Steam Generator Sample Steam Generator Sample Ye s

5 seconds 5 seconds

{hL l

2-EB-91 drogen Purge Yes 5 seconds e 2-EB-92 Ily en Purge Yes 5 seconds w

Ilydr 5 seconds "

1 2-EB-99 Purge Yes (i

. 2-EB-100 Ilydrogen e- Yes i 5 seconds _

B.

i f Y

MANUAL , \

2-SI-709* Shuld onling Yes Not Applicable- i 2-51-463* Safe Injection Tank Te line Yes Not Applicable E1 i P  :

tation Air Not Applicable 2-SA-19* Yes h

2-RW-21* Refueling Water Purification Yes Not Appilcable 2-RW-63* Refueling Water Purification Yes Not Applicable Refueling Water Purification Yes Net Appilcable e, 2-RW-154*

2-RW-232* Refueling Water Purification Yes Not Appilcable j El i

2-AC-46* Hydrogen Monitoring Yes t Applicable XI i

Hydrogen Monitoring Yes No pplicable k 2-AC-

  • Yes Not Ilcable

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g 2- -458* ArW Condensate Drain Not App able g -MS-459* AFW Condensate Drain Yes ~_

-o C. OTilER - NOT APPLICABLE O

e g *May be opened on an intermittent basis under administrative control.

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'.. htober 6,19

' CONTAINMENT SYSTEMS BASES 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3 /4. 6. 2.1 CONTAINMENT SPRAY SYSTE?1 The OPERABILITY of the containment spray system ensures that continin-ment depressurization and cooling capability will be available in the event of a LOCA. The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses. The leak rate surveillance requirements assure that the leakage assumed for the system outside containment during the recircula- a7 tion phase will not be exceeded.

3/4.6.2.2 CONTAINMENT AIR REC 1RCULATION SYSTEM The OPERABILITY of the containment cooling system ensures that

1) the containment air temperature will be maintained within limits during normal operation, and 2) adequate heat removal capacity is available when operated in conjunction with the containment spray systems during post-LOCA conditions.
3/4.6.3 CONTAINt1ENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the continment atmos-obere or pressurization of the con ainment. Containment isolation within

.P.he time limits specified ensures that the release of radioactive material

o the environment will be consisten . with the assumptions used in the _

hqalyses for a LOCA. ..

The containment purge supply and exhaust isolation valves are required to be closed and electrit. ally deactivated during plant operation since these valves have not been demonstrated capable of closing during a LOCA or steam fline break accident. Such a demonstration would require justification of - 47f

,;;he mechanical operability of the surge valves and consideration of the l' appropriateness of the electrical override circuits. Maintaining these iivalves closed during plant operatiens ensures that excessive quantities of

! radioactive materials will not be released,via the containment purge' system.

! 1rs:ut A U

fCLLSTONE - UNIT 2 53/46-3

g % ^5 tv4-The Technical Requirements Manual lists the containment isolation valves. The addition, deletion, or modification of any containment isolation valve or related information is reviewed under 10 CFR 50.59 and is approved by the Plant Operations Review Committee.

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Docket No. 50-336 B15479 l

l Attachment 4 Millstone Nuclear Power Station, Unit No. 2 Proposed Technical Specifications Revision Containment Isolation Valves l

Retyped Technical Specifications January 1996

. DEFINITIONS CONTAINMENT INTEGRITY 1.8 CONTAINNENT INTEGRITY shall exist when:

1.8.1 All penetrations required to be closed during accident conditions are either:

a. Capable of being closed by an OPERABLE containment automatic isolation valve system, or operator action during periods when containment isolation valves may be opened under administrative control per Specification 4.6.1.1.a. or
b. Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, 1.8.2 The equipment hatch is closed and sealed, and 1.8.3 The airlock is OPERABLE pursuant to Specification 3.6.1.3.

CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequen-tial, overlapping or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST 1.11 A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

MILLSTONE - UNIT 2 1-2 Amendment No.

0254

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,3/4.6. CONTAINMENT SYSTENS 3/4.6.1 PRIMARY CONTAIMENT CONTAIMENT INTEGRITY LIMITING CONDITION FOR OPERATIO;i 3.6.1.1 Primary CONTAINFBiT INTEGRITY shall be maintained.

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

ACTION:

Without primary CONTAINMENT INTEGRITY,* restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY 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 SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

l SUMEILLANCE REQUIRENENTS  :

1 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a. At least once per 31 days by verifying that all penetrations **

not capable of being closed by OPERABLE containment automatic isolation valves, or operator action during periods when containment isolation valves are opened under administrative control, and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves l secured in their positions.

b. At least once per 31 days by verifying the equipment hatch is l closed and sealed.
c. By verifying the containment air lock is OPERABLE per Specification 3.5.1.3.
d. After each closing of a penetration subject a type B testing ,

(except the containment air lock), if opened following a Type A or B test, by leak rate testing in accordance with the Containment Leakage Rate Testing Program.

  • 0peration within the time allowances of the ACTION statements of Specifica-tion 3.6.1.3 does not constitute a loss of CONTAINMENT INTEGRITY.
    • Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that sue.h verification need not be performed more often than once per 92 days.

NILLSTONE - UNIT 2 3/4 6-1 Amendment No. 4 , pp, 0266

. CONTAllMENT SYSTENS 3/4.6.3 CONTAINNENT ISOLATION VALVES LINITING CONDITION FOR OPERATION 3.6.3.1 The containment isolation valves shall be OPERABLE with isolation times less than or equal to the required isolation times.

APPLICABILITY: N0 DES 1, 2, 3 and 4.

ACTION:

With one or more of the isolation valve (s) inoperable, either: l

a. Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or
b. Isolate the affected penetration (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of a deactivated automatic valve (s) secured in the isolation position (s),or
c. Isolate the affected penetration (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of a closed manual valve (s) or blind flange (s); or
d. Be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

SURVEILLANCE REQUIP.ENENTS 4

4.6.3.1.1 Each isolation valve testable during plant operation shall be l l demonstrated OPERABLE:

a. At least once per 02 days by:
1. Exercising each power operated valve through one complete cycle of full travel and measuring the isolation time, and
2. Ecrcising each manual valve, except those that are closed, through one complete cycle of full travel.
b. Immediately prior to returning the valve to service after maintenance, repair or replacement work is performed on the l

, NILLSTONE - UNIT 2 3/46-15 Amendment No.

0266

. CONTAllelENT SYSTEMS i

SURVEILLANCE REQUIREMENTS (Continued) valve or its associated actuator, control or power circuit by performance of the applicable cycling test, above.

4.6.3.1.2 Each isolation valve shall be demonstrated OPERABLE during l the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

a. Verifying that on a containment isolation test signal, each isolation valve actuates to its isolation position, ,

i

b. Verifying that on a containment Radiation-High signal, all containment purge valves actuate to their isolation position,
c. Exercising each power operated valve not testable during plant operation, through one complete cycle of full travel and measuring its isolation time, and
d. Exercising each manual valve not locked, sealed or otherwise secured in position through at least one complete cycle of full travel.

I NILLSTONE - UNIT 2 3/4 6-16 Amendment No.

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MILLSTONE - WIT 2 3/4 6-17 Amendment No.

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E MILLSTONE - UNIT 2 3/4 6-18 Amendment No. JJ.

0266

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CONTAIMENT SYSTENS BASES l

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM l The OPERABILITY of the containment spray system ensures that contain-ment depressurization and cooling capability will be available in the i event of a LOCA. The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses. The leak rate surveillance requirements assure that the leakage assumed for the system outside containment during the recircula-tion phase will not be exceeded.

3/4.6.2.2 CONTAINMENT AIR RECIRCULATION SYSTEM  !

l The OPERABILITY of the containment cooling system ensures that

1) the containment air temperature will be maintained within limits during normal operation, and 2) adequate heat removal capacity is available when operated in conjunction with the containment spray systems during post-LOCA conditions.

3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the ,

containment atmosphere will be isolated from the outside environment in 2 the event of a release of radioactive material to the containment atmos-phere or pressurization of the containment. Containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.

The containment purge supply and exhaust isolation valves are required )

to be closed and electrically deactivated during plant operation since these  ;

valves have not been demonstrated capable of closing during a LOCA or steam '

line break accident. Such a demonstration would require justification of the mechanical operability of the purge valves and consideration of the appropriateness of the electrical override circuits. Maintaining these valves closed during plant operations ensures that excessive quantities of l radioactive materials will not be released via the containment purge system. '

The Technical Requirements Manual lists the containment isolation valves. l The addition, deletion, or modification of any containment isolation valve or related information is reviewed under 10 CFR 50.59 and is approved by the i Plant Operations Review Committee.

MILLSTONE - UNIT 2 B 3/4 6-3 Amendment No.

0267 i

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