ML17324A869

Amends 95 & 81 to Licenses DPR-58 & DPR-74,respectively, Changing Tech Specs for Testing Certain Containment Isolation Valves

ML17324A869
Person / Time
Site:	Cook
Issue date:	04/23/1986
From:	Youngblood B Office of Nuclear Reactor Regulation
To:
Shared Package
ML17324A860	List: ML17324A857 ML17324A864 ML17324A869
References
NUDOCS 8605020245
Download: ML17324A869 (34)

Text

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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment,No.

95 License No.

DPR-58 1.

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

A.

The application for amendment by Indiana and Michigan Electric Company (the licensee) dated October 19,

1984, as supplemented by letters dated May 31, 1985, October 18,

1985, and February 7, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

C.

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

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-58 is hereby amended to read as follows:

8605020245 860423 PDR ADOCK 050003i5 P

PDR

e (2)

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

95, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The change in Technical Specifications is to become effective within 60 days of issuance of the amendment.

In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensee shall adhere to the Technical Specifications for the systems, components, or operation existing at the time.

The period of time during changeover of systems, components or operation shall be minimized or compensated for by suitable temporary altergatives.

4.

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

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 23>> l986 W B. J.

Youngblood, Director PWR Project Directorate P4 Division of PWR Licensing-A, NRR

(2)

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

95, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The change in Technical Specifications is to become effective within 60 days of issuance of the amendment.

In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensee shall adhere to the Technical Specifications for the systems, components, or operation existing at the time.

The period of time during changeover of systems, components or operation shall be minimized or compensated for by suitable temporary alternatives.

4.

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

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

April ~3

>986 B. J.

Youngbl ood, Director PWR Project Directorate ¹4 Division of PWR L'icensing-A, NRR PWR¹4:

PWR-A DWig inton:mac 04/(

/86 4'WR-A oel ld Iss 04/

y-L /86 ysb>

PWR¹4:DPWR-A BJYoungblood 04/10 /86

T II

3.

4.

(2)

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 81, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

The change in Technical Specifications is to become effective within 60 days of issuance of the amendment.

In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensee shall adhere to the Technical Specifications for the systems, components, or operation existing at the time.

The period of time during changeover of systems, components or operation shall be minimized or comppjsated

'for by suitable temporary alternatives.

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

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 23, 1986 B. J.

Youngblood, Director PWR Project Directorate ¹4 Division of PWR Licensing-A, NRR PWR¹4:DPWR-A DWig. inton:mac 04/L

/86 PW

'WR-A O4/g,

/86 OEL r 04/)Q

/86 VS0 b PWR¹4:DPWR-A BJYoungblood 04/i~ /86

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t UNITED STATES t

NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

81 License No.

DPR-74 1.

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

A.

The application for amendment by Indiana and Michigan Electric Company (the licensee) dated October 19,

1984, as supplemented by letters dated May 31, 1985, October 18,

1985, and February 7,

1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission'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 Commission; C.

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 Commission'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 Commission's regulations and all applicable requirements have been satisfied.

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-74 is hereby amended to read as follows:

3.

4, (2)

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 81, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

The change in Technical Specifications is to become effective within 60 days of issuance of the amendment.

In the period between issuance of the amendment and the effective date of the new Technical Specifications,. the licensee shall adhere to the Technical Specifications for the systems, components, or operation existing at the time.

The period of time during changeover of systems, components or operation shall be minimized or compensated for by suitable temporary alternatives.

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

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 23, 1986 U+~

~ B. J.

Youngblood, Director PWR Project Directorate ¹4 Division of PWR Licensing-A, NRR

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.

95 FACILITY OPERATING LICENSE NO.

DPR-58 AMENDMENT NO.

81 FACILITY OPERATING LICENSE NO.

DPR-74 DOCKET NOS.

50-315 AND 50-316 Revise Appendix A as follows:

Remove Pa es UNIT I

'3/4 6-1 3/4 6-2*

3/4 6-14 3/4 6-15 3/4 6-16 3/4 6-17 3/4 6-18 3/4 6-19 3/4 6-20 3/4 6-21

'/4 6-22 UNIT 2 3/4 6-17 3/4 6-18 3/4 6-19 3/4 6-22 3/4 6-23 3/4 6-24 3/4 6-27*

3/4 6-28 3/4 6-29 3/4 6-30 3/4 6-31 Insert Pa es 3/4 6-1 3/4 6-2*

3/4 6-14 3/4 6-15 3/4 6-16 3/4 6-17 3/4 6-18 3/4 6-19 3/4 6-20 3/4 6-21 3/4 6-22 3/4 6-17 3/4 6-18 3/4 6-19 3/4 6-22 3/4 6-23 3/4 6-24 3/4 6-27*

3/4 6-28 3/4 6-29 3/4 6-30 3/4 6-31 Included for Convenience

3/4. 6 CONTAINMENT SYSi'EMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

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 following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REOUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a.

At least once per 31 days by verifying that:

1.

All penetrations*not capable of beinq closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanqes, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.3.1, and 2.

All equipment hatches are closed and sealed, b.

By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.

• 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 dur-ing each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days..

D.

C.

COOK-UNIT 1 3/4'6-1 Amendment No.

95

~

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CONTAINMENT SYSTEMS CONTAINYiENT LEAKAGE LIYiITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a.

An overall integrated leakage rate of <L, 0.25 pere nt by weight of the containm nt air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P, 12.0 psig, and b.

A combined leakage rate of <0.60 La for all penetrations and valv s subject to Type B and C tests when pressurized to P

APPLICABILITY:

YiODES 1, 2, 3 and 4.

ACTION:

1!ith either (a) the m asured overall.integrated containment leakage rate exceeding 0.75 La or (b) with the m asured combined leakage rate for all penetrations and valv s subject to Typos B and C tests exceeding 0.60 L

restore the leakage rate(s) to within the limit(s) prior to increasing the Reactor Coolant System temperature above 200'F.

SURVEILLANCE REOUIREMENTS 4.6.1.2 The containm nt leakage rates shall be demonstrated at the following t st schedule and shall be determined in conformance with the criteria sp cified in Appendix J of 10 CFR 50 using the mothods and provisions of ANSI N45.4-1972:

a.

Three Type A tests (Overall Integrated Containment Leakag Rate) shall be conducted at 40 + 10 month intervals during shutdown at P

, 12.0 psig, during each 10-year. service period.

The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection.

D.

C.

COOK-UNIT 1 3/4 6-2 Am ndment No.

18

CONTAItNENT SYSTHCS 3/4.6.3 CONTAINtIENT ISOLATION VALVES:.

LIHITIWG CONOITION FOR OPERATION 3.6.3.1 The containment isolation valves specified in Table 3.6-1.shall be OPERABLE with isolation times as shown in Table 3.6-1.

The ACTION statement of T/S 3/4.6.3 is not applicable to the containment purge sup-

'ply and exhaust isolation valves, VCR-101 through 106 and VCR-201 through

'206. listed in Table 3.6-1.

The Limiting Condition for Operation and its associated ACTION statement for these valves is given in Technical Speci-fication 3/4.6..1.7.

APPLICABILITY:

NODES 1, 2, 3 and 4.

ACTION:

Mith one or more of the isolation valve(s) specified in Table 3.6-1 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 Ce Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange, or d.

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 COLO

~

SHlJTDOMN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE'E UIREHENTS 4.6.3.1.1 The isolation valves specified in Table 3.6-1 shall be demonstrated OPERABLE prior to returning the valve to service after mainte-nance, repair or replacemerit work'is performed'on "the"valve oi its'associated actuator; control.or power circuit by performance of a cycling test and veri-fication of isolation time.

0. C. 'COOK-UNIT 1

~ 4

. 3/4 6-14 Amendment. No.

95

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) valve or its associated

actuator, control or power circuit by performance of the cycling test,

above, and verification of isolation time.

4.6.3.1.2 Each isolation valve soecified in Table 3.6-1 shall be demon-strated OPERABLE during 'the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

a.

Verifying that on q Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.

b.

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

c.

Verifying that on a Containment Purge and Exhaust isolation

signal, each Purge and Exhaust valve actuates to its isolation position.

4.6.3.1.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

D.

C.

COOK-UNIT 1 3/4 6-15 Amendment No.

95

VALVE NUtlBER A.

PHASE "A" ISOLATION TABLE 3.6-1 CONTAItNENT ISOLATION YALVES FUNCTION ISOLATION TINE-IN SECnNOS l.

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

12.

13.

14.

15.

16.

17.

18.

19.

20.

21.

22.

23.

24.

25.

26.

CCR-455 CCR-456 CCR-457 CCR-460 CCR-462 DCR-201 OCR-202 DCR-203 DCR-204 DCR-205 DCR-206 OCR-207 OCR-301 OCR-302 OCR-303 OCR-304 OCR-310 OCR-320 DCR-330 OCR-340 DCR-600 DCR-601 DCR-610 DCR-611 OCR-620 DCR-621 CCW to Peactor Supports CCW from Reactor Supports CCW from Reactor Suoports CCW from Excess ltdn. Hx.

CCW to Excess ltdn. Mx.

R.C. Drain Tank to Yent. Hdr.

R.C. Drain Tank to Gas Analyzer R.C. Drain Tank to Vent. Hdr.

R.C. Drain Tank to Gas Analyzer R.C. Drain Pump Suction Isolation R.C. Drain Pump Suction Isolation Nz Supply to R.C. Drain Tank Steam Generator Blowdown Sample Pl Steam Generator Blowdown Sample 82 Steam Generator Blowdown Sample 83 Steam Generator Blowdown Sample II4 Steam Generator Blowdown Lines II1 Steam Generator Blowdown Lines 82 Steam Generator Blowdown.Lines 83 Steam Generator Blowdown Lines 84 Containment Sump to Waste Holdup Containment Sump to Waste Holdup Ice Condenser Drain to Dra'in Hdr.

Ice Condenser Drain to Drain Hdr.

Continuous Ventilation Drain to Holdup Continuous Yentilation Drain to Holdup 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10

VAI,VE Ht)HRI:R FIIIICTTOII TMI.R 3.6-(

(~Cene lnued ISO).ATIO)I TIHE ttt nennlll)S C3 Cl tel CJ3 I

O h.

27.

28.

29.

30.

31.

32.

33.

34.

35.

36.

37 ~

38; 39.

40 4).

42.

43.

44 ~

45.

46.

4i7.

4I).

49e 50.

5).

52.

53 ~

54.

55.

56.

57.

58.

59.

&0 ~

&I.

62.

PIIASE "h" ECR-]0 FCtt-I I ECR-] 2 ECR-13 ECR-14 F.ctt-15 ECR-]6 L'Ctt-17 ECR-18 L'CR-19 ECR-20 ECIt-21 ECR-22

'CR-23 ECR-24 rcR-25 ECII-26 ECR-27 ECR-28 ECR-29 ECR-416 I'.CR-4]7 L'Ctt-496 ECR-497 EClt-535-ECR-536 CCIt-301 CCIt-3) 4

[CR-5 ICR-6 HCII-251 HCR-252 HC)t-253 HCIt-254 OCR-)05 IICIt-106 t"at.IITtnH (rene~tenno Cont.

I)2 Sample Return Cont.

II Sample - hir to Rec.

E Cont.

I)2 Sample - hir from Rec.

E 2

Cont ~

I)2 Sample Low. Cont ~ Vol.

Cont.

I)2 Sample - Lov. Cont. Vol~

Cont.

I)2 Sample - lip Cont. Vol Cont.

II Sample ttp Cont. Vol.

Cont.

))2 Sample - hir to Rcc.

M Cont.

II Samp]e - Air from Rec.

M Cont.

1)

Sample << Cont.

Dome Vol.

2 Cont.

))2 Sample - Ret.urn 2

Cont.

II Sample - hir to Rec.

E.

Cont.

]I Sample - hir fr. Rec.

E 2

Cont.

)I Sample - Lou Cont. Vo].

2 Cont.

I)2 Sample " I.oM Cont. Vol..

2 Cont ~

l)2 Sample - ltp'Cont. Vo).

Cont.

I)2 Saniple - Up Cont. Vol.

Cont, Il Sample - hir to Rec. )I.

Cont..

I)2 Sample - Air Fr. Itec. M.

2 Cont,.

I)2 Sample - Cont.

Dome Vol.

PAS Containment Srrnqi Saraple PAS Contalnraent Sump Snmp]e PAS Waste L)quid and Gas Return

-'AS )lasts Liqu)d and Cas Itcttlrll I'AS Containiacnt Cau Sample I'AS Contriinmcnt.Caa Sample H2 Supply to I'ressrrrizcr Relief Tank H2 Supply to Acciim<<lators Accumulators Sample Accimtulators Sample Sample I.ine from Steam Can. Outlet II.

Saiaple I.inc from Steam Ccn. Out]et J)2 Sample I.lne frrtm St:corn I'cn. Outlet t3 Sample I.lne form Stcain'Cen.

Outlet 04 Itot ).cg Samp]c

)tot I.cg Sample 10

]O 10

]0 IO 10 IO

)0 10 10 10

]0 IO 10 10 10 10 10 10 10 10 10

]0 10

)0 IO 10 10 In 10

]0'6 10

]'6'O

)0

I

~

LDKIIQl ISOLATION TI)$

~WKERK 63.

NCR,107 64 'CR-108 65 'CR-109 66 ~ NCR-110 67 NCR-252 68, PCR-40 69~ QCH-250 70+

QCH 350 71+ OCR-300 72 e OCR-301 73 OCR-919 74+

OCR-920 75'CR 100 76 ~

RCR 101 77 'CR-10 78+ TCR-11.

79e VCR>>20 80+ YCR-21 81 ~ ICR-100 82 ICR-101 83 ~ ICR 102 84 ICR-103 X.. PMIK PRZ Liquid Savile PRZ Liquid Saaple PRZ Stea>>

Sample PRZ Stea>> Saaple Pri>>ary Mater to Pressure Relief Tank Contai~nt Servioe Air RCP Seal Mater Disoharge RCP Seal Mater Disoharge Letdmrn to Letdown Hx.

Letdown to Letdown Hx.

Deaineralixed Mater Supply for Refueling Cavity De>>incr aliaed Mater Supply for Refueling Cavity PRZ Relief Tank to Oas Anal.

PRZ Relief Tank to Oas Anal.

Olyool Supply to tan Cooler Olyool Supply to Fan Cooler Olyool Supply fro>> tan Cooler

. Olyool Supply fro>> tan Cooler Control Air to Containrrent Control Air to Contai~nt Isolation Control Air to Containaant Isolation Control Air to Contain>>ent

'10

'10 10 10 10 10 15 15 1.0 10 10 10 10 10 10 10 10 10 10 10 10 10 1 ~

CCH-451 2

CCH-452 3,

OCH-453 4.

CbH-454 5.

CCH-458 6 ~

CCH-459 7.

BCR-31 8.

BCR-32 9

ECR-33 10, ECR-35 11 'CR-36 CCM fro>> RCP Oil Coolers CCM fro>> RCP Oil Coolers CCM fro>> RCP Theraal Barrier CCM fro>> RCP Ther>>al Barrier CCM to RCP Oil Coolers A Thecal Barrier'CM to RCP Oil Coolers A Thermal Barrier Containaent Airborne Radiation Monitor Containaent Airborne Radiation Monitor Containment Airbor'ne Radiation Monitor Containaent Airborne Radiation Monitor Containment, Airborne Radiation Monitor I

60 60 30 30 60 60 10 10 10 10 10

l y

)

TABI.F. 3.6-1 (Contin>>erf)

VAI.VE tfllHBER FIIHCT1nti ISOIATIOII TIIIE IH SFCOIIDS Ba PIIASF. "8" Isol~ATIoll cnntrmieil}

CI CI rc C

o 12.

13.

14.

15.

16.

17.

18.

19.

20.

21.

22.

23.

'. 24.

25.

26.

27.

28.

29.

30.

31.

32.

33.

34.

35.

36.

37 ~

38.

39.

40 'I.

42.

43.

WCR-9nl WCR-903 MCR-905 Mut-907 MCR-909 MCR-911

'MCR-913 MCR-915

'WCR-921

'MCR-923

'MCR-925 MCR-927 MCR-929 WCR-931 MCR-933 MCR-935 MCR-941 M(:R-942 WCR-943 MCR'-944 WCR-945 MCR-946 MCR-94r7 MCR-948 MCR-951 MCR-952 MCR-953 MCR-954 MCR-955 MCR-956 MCR-957 MCR-958 NF.SW NESM NESM HESM HLrSW HESM tiESM HESM HESW tlESM NESM NESM HESW NESW HESW tiESM HESM HESM HF.SM HESM tiESM IIESM HESM NESW HFSM tiESW HESM NESM HESM HL'SM tlESW tlESW

)1 l2

]3 l4 nt Il nt l2 nt l3 nt ff4 to 1aM Containment Vent fl from Lov Containment Vent ll to LoM Containment Vent l2 from l.oM Containment Vent f2 to l.ou Containment Vent f3 from LoM Containment Vent l3 to LoM Containment Vent l4 from Lou Containment Vent l4 to Up Containment Vent tl from Up Containment Vent fl to Up Containment Vent l2 from Up Containment Vent l2 to lfp Containment Vent t3 from Up Containment Vent l3 to Up Containment Vent l4 from Up Containment Vent t4 to RCP Hotor hlr Cooler to RCP Motor hir Cooler to RCP Hotor hir Cooler to RCP tfotor Air Cooler from RCP Hotor hir Cooler from RCP Motor hir Cooler from RCP Hotor hir Cooler from RCP tlotor hir Cooler to RCP tfotor hir Cooler Vent to RCP Hotor hir Cooler Vent to RCP Hotor Air'Cooler Vent to RCI'otor hir Cooler Vent from RCP Hotor Air Cooler Ve from RCP Hotor Air Cooler Ve from RCP Hotor Air Cooler Vc from RCP Hotor Air Cooler Ve 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 ln 10 10 10 I

I

'rrhLVB }JIJNAER FUNCTlON ThALE 3.6"l (Cnntkn>red)

ISOLATION TIlE IN SECONDS D.

PNASE <<D<< ISOIATIO}l Continrrcd n

noO pc 44

'5.

46, 47 ~

48.

49.

50

'1.

52 ~

53.

54.

55

'6

'7

~

58.

59 ~

60..

61

'2

'3

'4

'5

'6

'7

'CR-961

.MCR>>963

~

MCR-965 IJCR-967 MCR-900

'MCR-902 I.CR-904 MCR-906 MCR-908 MCR-910 gCR-912 MCR-914 MCR-920 MCR-922 WCR-924 MCR-926 IJCR-920 MCR-930 WCR-932 MCR-934 IJCR-960 WCR-962 MCR-964 WCR<<966 NESM

}lESW NESW NESM NESM NL'SlJ NESlJ

}lESW NL'SM

'NESW NESM

}lESlJ NESlJ NESM NESM NESW

}lESM NESW NESlJ

}lESIJ iNESW NESW NESW HESW to Instr.

Hm. Bast Vent from Instr. Rm. West Vent to Instr.

Hm. East Vent from Instr.

Rm. Mast Vent to RCP Lower Containrrrcnt Vent gl from Lower Containment Vent 01 to RCP Lower Containment Vent g2 from Lower Contairimcnt Vent 02 to RCP Lower Containmcnt Vent P3 from Lower Containment Vent P3 to RCP Lower Containmcnt Vent P4 from Lower Containment Vent 84 to RCP llpper Containment Vent dl from Upper Containment Vent Pl to RCP Upper Containment Vent N2 from Upper Containment Vent 02 to RCP Upper Containment Vent g3 from llppcr Containmcnt Vent P3 to RCP Upper Containment Vent g4 from Upper Containment Vent t4 to Instrument Room East Vent

'rom Instrument Room East Vent to Instrument Room Mast Vent from Instrument Room West Vent 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 C.

Co}JTAI}JHE}rrPlmrE ANn EXnhUST ~a O

Vl 1

2 ~

3 ~

4 ~

5 ~

6.

7 ~

8 ~

9.

10.

11.

VCR-101 VCR>>102 VCR-103 Vca-104 VCR-105 VCR-106 VCR-107*

VCR-201 VCR-202 VCR-203 VCR-204 Instr.

Room Prrrga Air Inlet I<<atr.

Room Purge hir Outlet Lower Comp. Purge Air Inlet Lower Comp. Purge hir Outlet Upper Comp. P<<rgc Air Inlet Upper Comp. Purge hir Outlet Cont. Presa.

Relief Fan Isolation Instr.

Room P<<rga hir Inlet Instr.

Room P<<rgc hir 0<<tlct l,ower Comp. P<<rgc hir Inlet Lower Comp. Piirge Air Outlet 5;

5 5

5 5

5

~

~

~

~

ISOLATION TIRt

~JOE!C5593 I

M 12+ VCR-205 13 'CR-206 1 I'CR 207e Upper Coxp. Purge Air Inlet Upper Coap.

Purge Air Outlet Cont. Press Relief Fan Isolation

~JEX o

n ft 0

1 ~

20 34 1 ~

5.'.

70 8.

"a 9~

10m 11 ~

12.

13

'I

~

15'6

~

17 ~

18'CH-111 ICH 129 ICH-250 ICH-251 ICH 260 ICH-265

'CH-305 ICH-306 ICH 311 ICH 321 NPX 151 VI PA 343 SF 151 SF-153 SF 159 SF 160 SI 171 SI 172 RHR to RC Cold Legs RHR Inlet to Pu~s Boron In)eotion Inlet

. Boron In)cation Inlet Safety Ingeotion Inlet Safety In)sation Inlet RHR Suotion frox Suxp RHR Suotion frox Suxp RHR to RC Hot Legs RHR to RC Rot Legs Dead Meight Tester Containxent Serrioe Air Refueling Mater Supply Refueling Mater Supply Refueling Carity Drain to Purifioation Systex Refueling Carity Drain to Purifioation Systex Safety Ingestion Test Line Aoouxuiator Test Line NA NA NA NA NA NA NA NA

.NA NA NA NA NA NA NA NA NA NA

Vhl.VE HlWlll!R FttttCTION TAMF. 3.!~i"I

~Cont f nuked

~e r D. Hhtttthl. ISOI.ATIOtt VhlVES

'ontinued (I)

ISOLATIOtt Tl1)E IH SECOtfDS l9.

20.

21 22

'3

'4

'5

'6; 27 ~

28.

, 29.

30 ~

CCR-440 CCR-441 HCH-221 BQt-231 CCH-430 CCH-431 CCtt-432 CD!-433 Stt-8>

SH-10+

SH"4>

Stt-&+

CCM from )tain Steam Penetration CCM from Hain Stcam Pcnctration Hain Steam to huxkliary Feed Pump Hain Stcam to Auxiliary Feed Pump CCQ to East Pressure Equalization Fan CCM from East Pressure Equalization Fan CCM to Meat,pressiire Equalization Fan CCM from Mast Prcssure Equalization Fan Upper Containment Sample Upper Containment Sample Instrument Boom Sample Instrument Room Sample Nh HA lih HA HA Nh Nh HA HA Nh

}th HA tth

- Honual Valve-Isolation time not applicable, (I)

'Includes motor operated valves vhich do not isolate automaticallyi

- Hay be opened on nn jntermittent basis under administrative control,

• • - Containment purge supply and.exhaust isolation va1vcs (VCR-101 through 106 and VCR-201 through 206) may ba opened under Tcchnical Spccificati n 3/4.6.1 7 ~

I I

I

TABLE 3.6-1 (Continued)

CONTAINMENT ISOLATION VALVES B

CD

~+

35.

36.

ECR-18 ECR-19 VALVE NUHBER A.

PHASE "A" ISOLATION n

25.

OCR-620 26.

OCR-621 27.

ECR-10 28.

ECR-11 29.

F.CR-12 30.

ECR-13 31.

ECR-14 32.

FCR-15 33.

ECR-16 34.

ECR-17 Cont.

Cont.

H2 Sample - Up. Cont. Vol.

H2 Sample - Up. Cont. Vol.

Cont.

H2 Sample - Air to Rec.

W Cont.

H2 Sample - Air from Rec.

W Cont.

H2 Sample - Cont.

Oome Vol.

FUNCTION.

(Continued)

Cont)nuous Vent)lat)on Dragon to Holdup Cont)nuous VentIlat)on Dra)n to Holdup Cont.

H2 Sample Return Cont.

H2 Sample - Air to Rec.

E Cont.

H2 Sample - Akr From Rec.

E Cont.

H2 Sample - Low. Cont. Vol.

Cont.

H2 Sample - Low. Cont. Vol.

ISOLATION TIHE IN ECONOS

< 10

< 10

< 10

< 10

< 10

< 10

< 10

< 10

< 10

< 10

< 10

< 10

COttTAINHEH'f ISQLATIOt1 VhLVES VAI'IIP. IlliHDLR F 1tNCTION ISOLATION TIME In SECOWS h.

PllhSE "h" ISOLATION (Continued)

~ W ClO 37.

ECR-20 30.

ECR-21 39.

Ectt-22 40.

ECR-23 41.

ECtt-24 42..

ECB-25 43.

ECR-26 44.

ECR-27 Ai5.

EClt-20 46.

ECB-29 Cont.

112 Sample-Return Cont.

112 Samp1e - hir to Rac.

E.

Cont.

Il2 Sample - hir Fr. Rec.

E.

Cont.

112*Sample - l.ou. Cont. Vol.

Cont.

112 Sample - Imv. Cont. Vol.

Cont.

B2 Sample - ltp. Cont. Vol..

Cont.

112 Sample - Up. Cont. Vol.

Cont.

112 Sample - Air to Rcc.

M.

Cont.

112 Sample - Air Fr.

Rec,.

M.

Cont.

112 Sample - Cont.

l)arne Vol.

c10 ci0 A

cl0 F10 ilO c,10 c10 clO O

CX>

47.

4B.

49.

50.

'5l.

'52.

53.

54.

ECR-416 EClt-417 ECB-496 EClt-497 ECB-535 Ectt-536 G(;tt-301 GCB-314 PAS Containment Sump Sample PAS Conta iniacnt S>>mp Sample PAS ffastc Liquid and Gas Bi.turn PAS ffaste Liquid and Gas ltcturn PAS Containment Gas Sample PAS Containment Gas Sample ll2 Siipply to Prcssur'irer Belief Tank tt2 Supply to Acc>>mulators cl0 clO c10

<10

<<10

<<10

<<]0

<<10'

TABLE 3.6-t (Cnntfnnnd)

COtfTAIMIEHT ISOLATIOlI VALVES n

C3 7C O

VALVE IIUHDKR A.

PIIASE "A" ISOLATION

.55.

ICR-5 56 1CR-6 IICA-251k HCA-252l 59.

HCA-253$

60.

IICA-2541 nCA-105 62 ~

HCA-106:

63 ~

t(CA-1QY 64.

IICR-106 65.

NCA-109 66.

IICR-1ln FUNCTION (Continued).

Accumulators Sample Accumulators Sample Sample Line from Steam Gen. Outlet Nl Sample Line from Steam Gen. Outlet Il Sample Line from Stcam Gcn. Outlet N3 Sample Line'rom Stcam Gcn. Outlet f4 llot I.eg Sample Itot Leg Sample PAZ Liquid Sample PRZ Liquid Sample PAZ Stcam Sample PAZ Stcam Sample ISOLATION TIHE III SECONDS

< 10

< 10

< 10

< 10,

< 10

< 10

< 10

< 10

< 10

< 10

. <10

< 10

pv TABI.E 3.6-I (Cont)nued CONTAINMENT ISOISTION VAI.VES VALVE NUMBER FUNCTION ISOLATION TIME IN SECONDS B.

PIIASE "B" ISOLATION Continved 12.

MCR-901 13.

MCR-903 MCR-905 15.

MCR-907 16.

~

. 17.

WCR-909 MCR<<911 MCR-913 1&.

ChI r M O

23%

MCR-927 19.

MCR-915 20.

MCR-921 21 'CR-923 22.

MCR-925 NESW to Low. Containment Vent fl NESM from Low. Containment Vent fl NESM to Lou. Containment Vent 82 NESM from Lou. Containment Vent N2 NESM to Lou. Containment Vent N3 NESM from Lou. Containment Vent N3 NESM to I.ov. Containment Vent l4 NESM from Lou Containment Vent E4 NESW to Up. Containment Vent PI NESM from Up. Containment Vent 81 NESW to Up. to Containment Vent )2 NESM from Up. Containment Vent N2 AI0 410 MO

<IO

TABLE 3.6-1 (Continued CONTAINMENT ISOLATION VALVES VALVE NUMBFR FUNCTION ISOLATION TIME IN SECONDS B. PHASE uOu ISOLATION Continued 24 'CR-929 25.

MCR-931 26.

MCR-933 27 MCR-935 28.

MCR-941 29 'CR-942 30.

MCR-943 31.

MCR-944 32.

MCR-945 33.

WCR-946 34.

MCR-947 35.

MCR-948 36.

MCR-951 37 'CR-952 38.

WCR-953 39.

WCR-954 I

NESW to Up. Containment Vent f3 NESM from Up. Containment Vent P3 HESM to Up. Containment Vent 84 NESM from Up. Containment Vent I4 NESW to RCP Motor hir Cooler HFSM to RCP Motor hir Cooler HESM to RCP Motor Air Cooler HESM to RCP Motor Air Cooler HESM from RCP Motor hir Cooler HESM from RCP Motor hir Cooler HESM from RCP Motor h)r Cooler HESM from RCP Motor hir Cooler NFSM to RCP Motor Air Cooler Vent ll NESM to RCP Motor Air Cooler Vent l2 NESM to RCP Motor Air Cooler Vent 83 NFSW to RCP Motor Air Cooler Vent N4 410

<10

<lo 510 510 510 ciao 410

<10

<10 Xlo

TABLE 3.6-1 (Continued CONTAINMENT ISOIATIOH VhLVES VALVE HOMBER FUNCTION ISOLATION TIME IH SECOHOS 40.

MCR>>955 41.

MCR-956 NESM from.RCP Motor Air Cooler Vent

$ 1 HESM from RCP Motor Air Cooler Vent P2 410

<10 oo 42 ~

g 43.

44, MCR-957 MCR-958 MCR-961 NESM from RCP Motor Air Cooler Vent l3 NESM from RCP Motor hir Cooler Vent N4 NESM to Instr.

Rm. East Vent

<10

<10 48.

49.

I 50.

MCR-900 MCR-902 MCR-.904 51 ~

MCR-906 ID

,52.

53 O

54.

MCR-908 MCR-910 MCR-912 55.

MCR-914 45.

MCR-963 46.

MCR-965 47.

MCR-967 NESM from Instr.

Rm. Meat Vent NESM to Instr.

Rm. East Vent NESM from Instr.

Rm. Meat Vent NESM to RCP l.over Containment Vent Nl NESM from Lover Containment Vent fl HESW to RCP l.over Containment Vent t2 NESM from Lover Containment Vent 82 HESW to RCP l.over Containment Vent 83 NESM from Lover Containment Vent S3 HESW to RCP Lover Containment Vent )4 NESW from I.over Containment Vent l4.

<10 410

<10 610

<10

<10 410

TABLE 3.6-1 (Continued)

CONTAINMFNT ISOLATION VALVES VALVE NUMBER D.

MANUAL ISOLATION VALVES 3.

1CM-250 4.

1CM-251 5.

1CM-260 6.

1CM-265 7.

1CM-305 8.

1CM-306 9.

1CM-3118 10.

1CM-3218 E.

OTHER CS-442-1 2.

CS-442-2 3.

CS-442-3 4.

CS-442-4 FUNCTION (Continued)

Boron Injection Inlet Boron Injection Inlet Safety Injection Inlet Safety Injection Inlet RHR Suction From Sump RHR Suction From Sump RHR to RC Hot Legs RHR to RC Hot Legs Seal Wtr. to RCP Pl Seal Wtr. to RCP P2 Seal Wtr. to RCP 'P3 Seal Wtr. to RCP P4 ISOLATION TIME IN SECONDS NA NA NA

THIS PAGE INTENTIONALLYLEFT BLANK D. C.'COOK - UNIT 2 3/4 6-28 Amendment No.

81

TABLE 3.6-1 (Continued)

CONTAINMENT ISOLATION VALVES VALVE NUMBER FUNCTION ISOLATION TIME IN SECONDS 5.

6.

7.

8.

SI-189 PA-342 NPX-151 VI N-160 9.

SM-1 10.

N-102 11.

SI-171 12 SI-172 13.

SI-194 14.

PW-275 15.

CS-321 E.

OTHER (Continued)

R. C. Reli'ef Valve Vent Hole Service Air to Containment Dead Weight Calibrator N2 to R. C. Drain Tank Air Particle/Radio Gas Detect Return N

To Accumulators Safety Injection Test Line Safety Injection Test Line Safety Injection Test Line Primary Wtr. to Pre. Relief Tank R.C.S. Charging NA NA NA NA NA NA NA NA NA NA

TABLE 3.6-1 (Continued)

CONTAINMENT ISOLATION VALVES VALVE NUMBER FUNCTION.

ISOLATION TIME IN SECONDS E.

OTHER (Continued) 16.

SF-152 17.

SF-154 18.

SF-159 19.

SF-160 20.

N-159 21.

CCW-135 22.

CA-181-N 23.

CA-181-S 24.

SM-8*

25.

SM-10*

Refueling Wtr. to Refuel Cavity Refueling Wtr. to Refuel Cavity Refueling Cavity Drain Refueling Cavity Drain N

to Prz. Relief Tank CCW to Reactor Supports Weld Channel Supply Air Weld Channel Supply Air Upper Cont. Grab Sample Upper Cont. Grab Sample NA NA NA NA NA NA NA NA

TABLE 3.6-1 (Continued)

CONTAINMENT ISOLATION VALVES VALVE NUMBER FUNCTION ISOLATION TIME IN SECONDS 32..

33.

34.

35.

Blind Flange Blind Flange Blind Flange Blind Flange E.

OTHER (Continued) 26.

PPP-300 27.

PPP-301 28.

PPP-302 29; PPP-303 30.

PPA-310 and PPA-311 31.

PPA-312 and PPA-313 Instrument Penetration Instrument Penetration Instrument Penetration Instrument Penetration Instrument Penetration Instrument Penetration Fuel Transfer Penetration Ice Condenser Ice Supply Ice Condenser Ice Return In-Core Flux Thimble Access NA NA NA NA NA NA NA NA NA NA