Text

Amends 197 & 188 to Licenses DPR-77 & DPR-79,respectively, Clarifying LCO Applicable to Dual Function of Containment Vacuum Relief Isolation Lines
	ML20087J323
Person / Time
Site:	Sequoyah ; (DPR-77-A-197, DPR-79-A-188)
Issue date:	04/28/1995
From:	Hebdon F; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20087J326	List: ML20087J323; ML20087J329;
References
	NUDOCS 9505080213
	Download: ML20087J323 (24)
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4 UNITED STATES p

g NUCLEAR REGULATORY COMMISSION e

WASHINGTON, D.C. 20h0001 o

+

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE000YAH NUCLEAR PLANT. UNIT 1

, AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.197 License No. DPR-77 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated March 19, 1993; which was superseded by letter dated May 16, 1994; which was superseded by letter dated February 10, 1995, with amplifying information being supplied by letter dated February 17, 1995; complies with the standards and requirements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 (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 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.

1 9505080213 950428 PDR ADOCK 05000327 l

P PDR

e l

. 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-77 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised 'through Amendment No.197, are hereby incorporated in the license.

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

4 3.

This license amendment is effective as of its date of issuance, to be implemented within 45 days.

FOR THE NUCLEAR REGULATORY COMMISSION

)

Frederick J. He on, Director Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications l

Date of Issuance: April 28, 1995 l

P

.o.

ATTACHMENT TO LICENSE AMENDMENT NO. 197 FACILITY OPERATING LICENSE NO. OPR-77 DOCKET NO. 50-327 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT VIII VIII l

XIII XIII l

3/4 6-17 3/4 6-17 3/4 0-21 3/4 6-21 3/4 6 'c2 3/4 6-22 3/4 6-t'1 3/4 6-23 i

3/4 6-;8 3/4 6-38 I

B3/4 6-3a B3/4 6-6 B3/4 6-6 I

i

4 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION Mq[

3/4.6.3 CONTAINMENT ISOLATION VALVES..............................

3/4 6-17 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Monitors.........................................

3/4 6-24 Electric Hydrogen Recombiners.............................

3/4 6-25 3/4.6.5 ICE CONDENSER Ice Bed...................................................

3/4 6-26 Ice Bed Temperature Monitoring System.....................

3/4 6-28 Ice Condenser Doors.......................................

3/4 6-29 Inlet Door Position Monitoring System.....................

3/4 6-31 Divider Barrier Personnel Access Doors and Equipment Hatches.......................................

3/4 6:32 Containment Air Return Fans...............................

3/4 6-33 Fl o o r D r a i n s..............................................

3/4 6-34 Re fuel i ng Can al Dra i n s.................................... 3/4 6-35 Divider Barrier Seal......................................

3/4 6-36 3/4.6.6 VACUUM RELIEF LINES.......................................

3/4 6-38 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYC'LE S a f e ty V a l v e s.............................................

3/4 7-1 Auxiliary Feedwater System................................

3/4 7-5 Condensate Storage Tank...................................

3/4 7-7 Activity..................................................

3/4 7-8 1

Main Steam Line Isolation Valves..........................

3/4 7-10 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...........

3/4 7-11 3/4.7.3 COMPONENT COOLING WATER SYSTEM............................

3/4 7-12 3/4.7.4 ESSENTIAL RAW COOLING WATER SYSTEM Essenti al Raw Cooling Water System........................

3/4 7-13 SEQUOYAH - UNIT 1 VIII Amendment No. 116, 197

l f

INDEX BASES i

SECTION f1GE 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE.............................

B 3/4 4-4 3/4.4.7 CHEMISTRY..................................................

B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY..........................................

B 3/4 4-5 3/4.4.9 PRESSURE 7TEMPERATURELIMITS................................

B 3/4 4-6 3/4.4.10 STRUCTURAL INTEGRITY......................................

B 3/4 4-14 3/4.4.11 REACTOR COOLANT SYSTEM HEA0 VENTS.........................

B 3/4 4-14 3/4.4.12 OVERPRESSURE PROTECTION SYSTEMS...........................

B 3/4 4-14 l

3/4.5 EMERGENCY CORE COOLING SYSTEMS i

3/4.5.1 ACCUMULATORS...............................................

B 3/4 5-l j

3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS................................

B 3/4 5-l 3/4.5.4 BORON INJECTION SYSTEM.....................................

B 3/4 5-2 3/4.5.5 REFUELING WATER STORAGE TANK...............................

B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS i

3/4.6.1 PRIMARY CONTAINMENT........................................

B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.......................

B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES...............................

B 3/4 6-3 3/4.6.4 COMBUSTIBLE GAS CONTR0L....................................

B 3/4 6-3 3/4.6.5 ICE CONDENSER..............................................

B 3/4 6-4 3/4.6.6 VACUUM RELIEF LINES........................................

B 3/4 6-6 l

3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE..............................................

B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE /TEMERATURE LIMITATION.............

B 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM.............................

B 3/4 7-3 i

l SEQUOYAH - UNIT 1 XIII Amendment No. 157, 197

[;

CONTAINMENT SYSTEMS l

3/4.6.3 CONTAINMENT ISOLATION VALVES 11tiLURLC.QHDlIlQtiJOR OPERATION 3.6.3 -The containment isolation valves specified in Table 3.6-2 shall be OPERABLE with isolation times as shown in Table 3.6-2.

APPLICABILITY: MQDES 1, 2, 3 and 4.

i ACTION:

a.

With one or more of the isolation valve (s) specified in Sections A, B, C l

and D.4 through D.7 of Table 3.6-2 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either:

1.

Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or

[

2.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one deactivated automatic valve secured in the isolation position, or i

i 3.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or blind flange; or 4.

Be in 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , b.

With one or more containment vacuum relief isolation valve (s) specified in Sections D.1 through D.3 of Table 3.6-2 inoperable, the valve (s) must be returned to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or be in at least HOT STANDBY J

within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 4

hours.

i SURVEILLANCE RE0VIREMENTS 4.6.3.1 The isolation valves specified in Table 3.6-2 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time.

l SEQUOYAH - UNIT 1 3/4 6-17 Amendment No.12,197

TABLE 3.6-2 (Continued) j wg CONTAIMENT ISOLATION VALVES 8

VALVE NUMBER FUNCTION MAXIMUM ISOLATION TIME (Seconds) g i

A.

PHASE "A" ISOLATION (Cont.)

s 61.

FCV-71-19 RCDT and PRT'to V H 10*

62. FCV-77-20 N to RCDT 10*

63 FCV-77-127 FioorSumpPumpDisch 10*

~

64. FCV-77-128 Floor Susp Pump Disch 10*

i

65. FCV-81-12 Primary Water Makeup 10*

l B.

PHASE "B" ISOLATION 1.

FCV-32-80 Control Air Supply 10 2.

FCV-32-102 Control Air Supply 10 3.

FCV-32-110 Control Air Supply 10 g

4.

FCV-67-83 ERCW - LWR Capt Cirs 60*

5.

FCV-67-87 ERCW - LWR Capt Clrs 60*

p 6.

FCV-67-88 ERCW - LWR Capt Clrs 60*

m 7.

FCV-67-89 ERCW - LWR Capt Clrs 70*

l 8.

FCV-67-90 ERCW - LWR Capt Clrs 70*

I 9.

FCV-67-91 ERCW - LWR Capt Clrs 60*

10. FCV-67-95 ERCW - LWR Capt Clrs 60*

r

11. FCV-67-96 ERCW - LWR Capt Clrs 60*

g

12. FCV-67-99 ERCW - LWR Capt Clrs 60*

o-

13. FCV-67-103 ERCW - LWR Capt Clrs 60*

l

14. FCV-67-104 ERCW - LWR Capt Clrs 60*

15. FCV-67-105 ERCW - LWR Capt Clrs 70*

g

16. FCV-67-106 ERCW - LWR Capt Clrs 70*

17. FCV-67-107 ERCW - LWR Capt Clrs 60*

y

18. FCV-67-111 ERCW - LWR Capt Cirs 60*

19. FCV-67-Il2' ERCW - LWR Capt Clrs 60*

y

20. FCV-67-130 ERCW - Up Capt Clrs 60*

21. FCV-67-131 ERCW - Up Capt Clrs 60*

1 co

22. FCV-67-133 ERCW - Up Capt Clrs 60*

23. FCV-67-134 ERCW - Up Capt Clrs 60*

24. FCV-67-138 ERCW - Up Capt Clrs 60*

P Q~

_ - _ _ _. _ _ _ =

TABLE 3.6-2 (Continued) mE CONTAIMEk N-

'TLQN VALVES 8

j VALVE NUMBER FUNCTI0n MAXIMUM ISOLATION TINE (Seconds)

[

B.

PHASE "B" ISOLATION (Cont.)

zZ

25. FCV-67-139 ERCW - Up Cent Clrs 60*

26. FCV-57-141 ERCW - Up Capt Clrs 60*

27. FCV-67-142 ERCW - Up Capt Clrs 60* "

28. FCV-67-295 ERCW - Up Capt Clrs 60*

l

29. FCV-67-296 ERCW - Up Capt Clrs 60*

30. FCV-67-297 ERCW - Up Capt Clrs 60*

31. FCV-67-298 ERCW - Up Capt Clrs 60*

32. FCV-70-87 RCP Thermal Barrier Ret 60

33. FCV-70-89 CCS from RCP Oil Coolers 60

34. FCV-70-90 RCP Thermal Barrier Ret 60

35. FCV-70-92 CCS from RCP Oil Coolers 60

36. FCV-70-134 To RCP Thermal Barriers 60

37. FCV-70-140 CCS to RCP 011 Coolers 60

?

38. FCV-70-141 CCS to RCP Oil Coolers 65 C.

PHASE "A" CONTAIMENT VENT ISOLATION 1.

FCV-30-7 Upper Compt Purge Air Supply 4*

2.

FCV-30-8 Upper Compt Purge Air Supply 4*

g 3.

FCV-30-9 Upper Compt Purge Air Supply 4*

5 4.

FCV-30-10 Upper Compt Purge Air Supply 4*

E 5.

FCV-30-14 Lower Compt Purge Air Supply 4*

2 6.

FCV-30-15 Lower Compt Purge Air Supply 4*

5 7.

FCV-30-16 Lower Compt Purge Air Supply 4*

z 8.

FCV-30-17 Lower Compt Purge Air Supply 4*

9.

FCV-30-19 Inst Room Purge Air Supply 4*

w

10. FCV-30-20 Inst Room Purge Air Supply 4*

11. FCV-30-37 Lower Compt Pressure Relief 4*

12. FCV-30-40 Lower Compt Pressure Relief 4*

?

TABLE 3.6-2 (Continuedl CONTAINMENT ISOLATION VALVES VALVE NUMBER FUNCTION MAXIMUM ISOLATION TIME (Seconds)

C.

PHASE "A" CONTAINMENT VENT ISOLATION (Cont.)

7 13.

FCV-30-50 Upper Compt Purge Air Exh 4*

14.

FCV-30-51 Upper Compt Purge Air Exh 4*

cz 15.

FCV-30-52 Upper Compt Purge Air Exh 4*

16.

FCV-30-53 Upper Compt Purge Air Exh 4*

17.

FCV-30-56 Lower Compt Purge Air Exh 4*

18.

FCV-30-57 Lower Compt Purge Air Exh 4*

19.

FCV-30-58 Inst Room Purge Air Exh 4*

20.

FCV-30-59 Inst Room Purge Air Exh 4*

21.

FCV-90-107 Cntmt Bldg LWR Compt Air Mon 5*

22.

FCV-90-108 Cntmt Bldg LWR Compt Air Mon 5*

23.

FCV-90-109 Cntmt Bldg LWR Compt Air Mon 5*

24.

FCV-90-Il0 Cntmt Bldg LWR Compt Air Mon 5*

25.

FCV-90-Ill Cntmt Bldg LWR Compt Air Mon 5*

26.

FCV-90-Il3 Cntmt Bldg UPR Compt Air Mon 5*

27.

FCV-90-Il4 Cntmt Bldg UPR Compt Air Mon 5*

28.

FCV-90-Il5 Cntet Bldg UPR Compt Air Mon 5*

?

29.

FCV-90-ll6 Cntmt Bldg UPR Compt Air Mon 5*

O 30.

FCV-90-Il7 Cntmt Bldg UPR Compt Air Mon 5*

g D.

OTHER k

1.

FCV-30-46 Vacuum Relief Isolation Valve 25 2

2.

FCV-30-47 Vacuum Relief Isolation Valve 25 a

3.

FCV-30-48 Vacuum Relief Isolation Valve 25 4.

FCV-30-571 Vacuum Relief Valve 2

P 5.

FCV-30-572 Vacuum Relief Valve 6.

FLV-30-573 Vacuum Relief Valve w

7.

FCV-62-90 Normal Charging Isolation Valve 12 5

Provisions of LCO 3.0.4 are not applicable if valve is secured in its isolated position with power removed 2

and leakage limits of Specification 4.6.1.1.c are satisfied. For purge valves, leakage limits under Surveillance Requirement 4.6.1.9.3 must also be satisfied.

.~

Provisions of LCO 3.0.4 are not applicable if valve is secured in its isolated position with power removed and either FCV--62-73 or FCV-62-74 is maintained operable.,

M

- Vacuum relief valves perform a containment isolation function. The maximum isolation time is not l

applicable to these normally closed self-acting valves.

CONTAINMENT SYSTEMS 3/4.6.6 VACUUM RELIEF LINES LIMITING CONDITION FOR OPERATION 3.6.6 Three primary containment vacuum relief lines shall be OPERABLE.*

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one primary containment vacuum relief line inoperable, restore the line to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.6.1 No additional surveillance requirements other than those required by Specification 4.0.5 1

Refer to LC0 3.6.3 if one or more containment vacuum relief isolation or containment vacuum relief valves are incapable of performing a containment isolation function.

SEQUOYAH - UNIT 1 3/4 6-38 Amendment No. 197

e CONTAINMENT SYSTEMS BASES Note that due to competing requirements and dual functions associated with the containment vacuum relief isolation valves (FCV-30-46, -47, and -48), the air supply and solenoid arrangement is designed such that upon the unavailabil-ity of Train A essential control air, the containment vacuum relief isolation valves are incapable of automatic closure and are theiefore considered inoperable for the containment isolstion function without operator action.

The containment vacuum relief valves (30-571, -572, and -573) are qualified to perform a containment isolation function. These valves are not powered from any electrical source and no spurious signal or operator action could initiate opening. The valves are spring loaded, swing disk (check) valves with an elastomer seat. The valves are normally closed and are equipped with limit switches that provide fully open and fully closed indication in the main control room (MCR). Based upon the above information, a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months allowed action time is appropriate while actions are taken to return the containment vacuum relief isolation valves to service.

t SEQUOYAH - UNIT 1 B 3/4 6-3a Amendment No. 197

CONTAINMENT SYSTEMS BASES l

3/4.6.5.7 and 3/4.6.5.8 FLOOR AND REFUELING CANAL DRAINS l

The OPERABILITY of the ice condenser floor and refueling canal drains ensures that following a LOCA, the water from the melted ice and containment spray system has access for drainage back to the containment lower compartment and subsequently to the sump. This condition ensures the availability of the water for long term cooling of the reactor during the post accident phase.

1 3/4.6.5.9 DIVIDER' BARRIER SEAL The requirement for the divider barrier seal to be OPERABLE ensures that a minimum bypass steam flow will occur from the lower to the upper containment compartments during a LOCA. This condition ensures a diversion of steam through the ice condenser bays that is consistent with the LOCA analyses.

3/4.6.6 VACUUM RELIEF LINES The OPERABILITY of three primary containment vacuum relief lines ensures that the containment internal pressure does not become more negative than 0.1 psid. This condition is necessary to prevent exceeding the containment design limit for internal vacuum of 0.5 psid. A vacuum relief line consists of a self-actuating vacuum relief valve, a pneumatically operated isolation valve,-

associated piping, and instrumentation and controls.

SEQUOYAH - UNIT 1 B 3/4 6-6 Amendment No.197

)

Mau 4

UNITED STATES y-g g

NUCLEAR REGULATORY COMMISSION t

WASHINGTON, D.C. 20555 0001

\\...../

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE000YAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.188 License No. DPR-79 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated March 19, 1993; which was superseded by letter dated May 16, 1994; which was superseded by letter dated February 10, 1995, with amplifying information being supplied by letter dated February 17, 1995; 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 Commission; 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 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.

1 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-79 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.188, 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 its date of issuance, to be implemented within 45 days.

e FOR THE NUCLEAR REGULATORY COMISSION i

W

=

Frederick J. Hebdo'fi, Director Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor' Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 28, 1995 l

l

\\

ATTACHMENT TO LICENSE AMENDMENT NO. 188 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the. captioned amendment number and contain marginal lines indicating the area of change.

i REMOVE INSERT VIII VIII XIII XIII 3/4 6-17 3/4 6-17 3/4 6-21 3/4 6-21 3/4 6-22 3/4 6-22 3/4 6-23 3/4 6-23 3/4 6-39 3/4 6-39 B3/4 6-3a B3/4 6-6 B3/4 6-6 1

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS l

SECTION Egf 3/4.6.3 CONTAINMENT ISOLATION VALVES..............................

3/4 6-17 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Monitors.........................................

3/4 6-24 Electric Hydrogen Recombiners.............................

3/4 6-25 Hydroge'n Control Interim Distributed Ignition System.....

3/4 6-26 3/4.6.5 ICE CONDENSER Ice Bed...................................................

3/4 6-27 Ice Bed Temperature Monitoring System.........~............

3/4 6-29 Ice Condenser Doors.......................................

3/4 6-30 Inlet Door Position Monitoring System.....................

3/4 6-32 Divider Barrier Personnel Access Doors and Equipment Hatches.......................................

3/4 6-33 Containment Air Return Fans...............................

3/4 6-34 Fl oo r D ra i n s..............................................

3/4 6-35 l

Re fuel i ng Canal Drai n s....................................

3/4 6-36 Di vide r Barri er Se al......................................

3/4 6-37 I

3/4.6.6 VACUUM RELIEF LINES.......................................

3/4 6-39 l

3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves.............................................

3/4 7-1 Auxiliary Feedwater System.....,..........................

3/4 7-5 Condensate Storage Tank...................................

3/4 7-?

Activity..................................................

3/4 7-8 Main Steam Line Isol ation Valves..........................

3/4 7-10 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...........

3/4 7-11 3/4.7.3 COMP 0NENT COOLING WATER SYSTEM............................

3/4 7-12 l

SEQUOYAH - UNIT 2 VIII Amendment No.188 r

INDEX BASES SECTION E&EE 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE.............................

B 3/4 4-4 3/4.4.7 CHEMISTRY..................................................

B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY..........................................

B 3/4 4-5 3/4.4.9 PRESSURE /TEMPERATURELIMITS................................

S 3/4 4-6 3/4.4.10 STRUCTURAL INTEGRITY......................................

B 3/4 4-14 3/4.4.11 REACTOR COOLANT SYSTEM HEAD VENTS.........................

B 3/4 4-15 3/4.4.12 OVERPRESSURE PROTECTION SYSTEMS...........................

B 3/4 4-15 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS...............................................

B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS................................

B 3/4 5-1 3/4.5.4 BORON INJECTION SYSTEM.....................................

B 3/4 5e2 3/4.5.5 REFUELING WATER STORAGE TANK...............................

B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT........................................

B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.......................

B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES...............................

B 3/4 6-3 3/4.6.4 COMBUSTIBLE GAS CONTR0L....................................

B 3/4 6-3 3/4.6.5 ICE CONDENSER..............................................

B 3/4 6-4 3/4.6.6 VACUUM RELIEF LINES........................................

B 3/4 6-6 l

3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE..............................................

B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE /TEMERATURE LIMITATION.............

B 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM.............................

B 3/4 7-3 l

SEQUOYAH - UNIT 2 XIII Amendment No. 147, 188

i CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING C0fEITION FOR OPERATION 3.6.3 The containment isolation valves specified in Table 3.6-2 shall be OPERABLE with isolation times as shown in Table 3.6-2.

APPLICABILITY: MODES 1, 2, 3 and 4.

i ACTION:

l a.

With one or more of the isolation valve (s) specified in Sections A, B, C and D.4 through D.7 of Table 3.6-2 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either:

j 1.

Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or 2.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one deactivated automatic valve secured in the isolation position, or

~

3.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or blind flange; or 4.

Be in 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With one or more containment vacuum relief isolation valve (s) specified in Sections D.1 through D.3 of Table 3.6-2 inoperable, the valve (s) must be returned to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or be in 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 i,JLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.3.1 The isolation valves specified in Table 3.6-2 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation

time, i

lI f

f I

SEQUOYAH - UNIT 2 3/4 6-17 Amendment No.188

TABLE 3.6-2 (Continued) o CONTAINMENT ISOLATION VALVES VALVE NUMBER FUNCTION MAXIMUM ISOLATION TIME (Seconds)

[

A.

PHASE "A" ISOLATION (Cont.)

zZ

61. FCV-77-19 RCDT and PRT to V H 10*

na 62.

FCV-77-20 N to RCDT 10*

63 FCV-77-127 FloorSumpPumpDisch 10*

64.

FCV-77-128 Floor Sump Pump Disch 10*

65.

FCV-81-12 Primary Water Makeup 10*

B.

PHASE "B" ISOLATION 1.

FCV-32-80 Control Air Supply 10 2.

FCV-32-103 Control Air Supply 10 3.

FCV-32-Ill Control Air Supply 10 m;

4.

FCV-67-83 ERCW - LWR Capt Clrs 60*

5.

FCV-67-87 ERCW - LWR Capt Clrs 60*

4 6.

FCV-67-88 ERCW - LWR Capt Clrs 60*

7.

FCV-67 ERCW - LWR Capt Clrs 70*

8.

FCV-67-90 ERCW - LWR Capt Clrs 70*

k 9.

FCV-67-91 ERCW - LWR Capt Clrs 60*

g

10. FCV-67-95 ERCW - LWR Capt Clrs 60*

g

11. FCV-67-96 ERCW - LWR Capt Clrs 60*

=

12. FCV-67-99 ERCW - LWR Capt Clrs 60*

13. FCV-67-103 ERCk - LWR Capt Clrs 60*

,E

14. FCV-67-104 ERCW - LWR Capt Clrs 60*

15.

FCV-67-105 ERCW - LWR Capt Clrs 70*

7,,e 16.

FCV-67-106 ERCW - LWR Capt Clrs 70*

l 17.

FCV-67-107 ERCW - LWR Capt Clrs 60*

E

18. FCV-67-111 ERCW - LWR Capt Clrs 60*

19. FCV-67-Il2 ERCW - LWR Capt Clrs 60*

E 20.

FCV-67-130 ERCW - Up Capt Clrs 60*

~

21. FCV-67-131 ERCW - Up Capt Clrs 60*

O

22. FCV-67-133 ERCW - Up Capt Clrs 60*

23. FCV-67-134 ERCW - Up Capt Clrs 60*

O

24. FCV-67-138 ERCW - Ua Capt Clrs 60*

M

TABLE 3.6-2 (Continued)

Mg CONTAINMENT ISOLATION VALVES VALVE NUMBER FUNCTION MAXIMUM ISOLATION TIME (Seconds)

B.

PHASE "B" ISOLATION (Cortt.)

U 25.

FCV-67-139 ERCW - Up Capt Clrs 60*

N 26.

FCV-67-141 ERCW - Up Capt Clrs 60*. '

27.

FCV-67-142 ERCW - Up Capt Clrs 60*

28. FCV-67-295 ERCW - Up Capt Clrs 60*

29.

FCV-67-296 ERCW - Up Capt Clrs 60*

30. FCV-67-297 ERCW - Up Capt Clrs 60*

31.

FCV-67-298 ERCW - Up Capt Clrs 60*

32.

FCV-70-87 RCP Thermal Barrier Ret 60 33.

FCV-70-89 CCS from RCP Oil Coolers 60 34.

FCV-70-90 RCP Thennal Barrier Ret 60 35.

FCV-70-92 CCS from RCP 011 Coolers 60 m2 36.

FCV-70-134 To RCP Thermal Barriers 60 37.

FCV-70-140 CCS to RCP Oil Coolers 60

.4 38.

FCV-70-141 CCS to RCP 011 Coolers 65 m

C.

PHASE "A" CONTAINMENT VENT ISOLATION 1.

FCV-30-7 Upper Compt Purge Air Supply 4*

2.

FCV-30-8 Upper Compt Purge Air Supply 4*

3.

FCV-30-9 Upper Compt Purge Air Supply 4*

4.

FCV-30-10 Upper Compt Purge Air Supply 4*

5.

FCV-30-14 Lower Compt Purge Air Supply 4*

g 6.

FCV-30-15 Lower Compt Purge Air Supply 4*

g 7.

FCV-30-16 Lower Compt Purge Air Supply 4*

g 8.

FCV-30-17 Lower Compt Purge Air Supply 4*

g 9.

FCV-30-19 Inst Room Purge Air Supply 4*

10. FCV-30-20 Inst Room Purge Air Supply 4*

g:

11. FCV-30-37 Lower Compt Pressure Relief 4*

12. FCV-30-40 Lower Compt Pressure Relief 4*

.O!

0

7 TABLE 3.6-2 (Continued)

CONTAINMENT ISOLATION VALVES v.

VALVE NUMBER FUNCTION MAXIMUM ISOLATION TIME (Seconds) h C.

PHASE "A" CONTAINMENT VENT ISOLATION (Cont.)

13.

FCV-30-50 Upper Compt Purge Air Exh 4*

E 14.

FCV-30-51 Upper Compt Purge Air Exh 4*

Z 15.

FCV-30-52 Upper Compt Purge Air Exh 4*

16.

FCV-30-53 Upper Compt Purge Air Exh 4*

~

17.

FCV-30-56 Lower Compt Purge Air Exh 4'*

18.

FCV-30-57 Lower Compt Purge Air Exh 4*

19.

FCV-30-58 Inst Room Purge Air Exh 4*

20.

FCV-30-59 Inst Room Purge Air Exh 4*

21.

FCV-90-107 Cntmt Bldg LWR Compt Air Mon 5*

22.

FCV-90-108 Cntet Bldg LWR Compt Air Mon 5*

23.

FCV-90-109 Cntmt Bldg LWR Compt Air Mon 5*

24.

FCV-90-110 Cntmt Bldg LWR Compt Air Mon 5*

25.

FCV-90-Ill Cntat Bldg LWR Compt Air Mon 5*

w 26.

FCV-90-Il3 Cntet Bldg UPR Compt Air Mon 5*

1 27.

FCV-90-Il4 Cntmt Bldg UPR Compt Air Mon 5*

os 28.

FCV-90-Il5 Cntet Bldg UPR Compt Air Mon 5*

d.

29.

FCV-90-116 Cntet Bldg UPR Compt Air Mon 5*

30.

FCV-90-Il7 Cntmt Bldg UPR Compt Air Mon 5*

D.

OTHER E

1.

FCV-30-46 Vacuum Relief Isolation Valve 25 E

2.

FCV-30-47 Vacuum Relief Isolation Valve 25 E

3.

FCV-30-48 Vacuum Relief Isolation Valve 25 E

4.30-571 Vacuum Relief Valve 5.30-572 Vacuum Relief Valve I

6.30-573 Vacuum Relief Valve

(

7.

FCV-62-90 Normal Charging Isolation Valve 12

[

Provisions of LCO 3.0.4 are not applicable if valve is secured in its isolated position with power removed y

and leakage limits of Specification 4.6.1.1.c are satisfied. For purge valves, leakage limits under surveillance Requirement 4.6.1.9.3 must also be satisfied.

Provisions of LC0 3.0.4 are not applicable if valve is secured in its isolated position with power removed g

and either FCV-62-73 or FCV-62-74 is maintained operable..

- Vacuum relief values perform a containment isolation function. The maximum isolation time is not

~

y applicable to these normally closed self-acting valves.

CONTAINMENT SYSTEMS 3/4.6.6 VACUUM RELIEF LINES LIMITING CONDITION FOR OPERATION l

3.6.6 Three primary containment vacuum relief lines shall be OPERABLE.*

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION.

With one primary containment vacuum relief line inoperable, restore-the line to OPERATE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

j SURVEILLANCE RE0VIREMENTS 4.6.6.1 No additional surveillance requirements other than those required by Specification 4.0.5.

l i

Refer to LCO 3.6.3 if one or more containment vacuum relief isolation or containment vacuum relief valves are incapable of performing a containment isolation function.

SEQUOYAH - UNIT 2 3/4 6-39 Amendment No.188

CONTAINMENT SYSTEMS BASES Note that due to competing requirements and dual functions associated with i

the containment vacuum relief isolation valves (FCV-30-46, -47, and -48), the air supply and solenoid arrangement is designed such that upon the unavail-ability of Train A essential control air, the containment vacuum relief isolation vales are incapable of automatic closure and are therefore considered inoperable for the containment isolation function without operator action.

The containment vacuum relief valves (30-571, -572, and -573) are qualified to perform a containment isolation function. These valves are not powered from any electrical source and no spurious signal or operator action could initiate opening. The valves are spring loaded, swing disk (check) valves with an elastomer seat. The valves are normally closed and are equip >ed with limit switches that provide fully open and fully closed indication in tie main control room (MCR).

Based upon the above information, a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months allowed action time is appropriate while actions are taken to return the containment vacuum relief isolation valves to service.

SEQUOYAH - UNIT 2 8 3/4 6-3a Amendment No. 188

CONTAINMENT SYSTEMS

]

BASES 3/4.6.5.7 and 3/4.6.5.8 FLOOR AND REFUELING CANAL DRAINS The OPERABILITY of the ice condenser floor and refueling canal drains ensures that following a LOCA, the water from the melted ice and containment spray system has iccess for drainage back to the containment lower compartment and subsequently to the sump. This condition ensures the availability of the water for long term cooling of the reactor during the post accident phase.

3/4.6.5.9 DIVIDER BARRIER SEAL The requirement for the divider barrier seal to be OPERABLE ensures that a minimum bypass steam flow will occur from the lower to the upper containment compartments during a LOCA. This condition ensures a diversion of steam j

through the ice condenser bays that is consistent with the LOCA analyses.

1 3/4.6.6 VACUUM RELIEF LINES The OPERABILITY of three primary containment vacuum relief lines ensures:

that the containment internal pressure does not become more negative than 0.1 psid.

This condition is necessary to prevent exceeding the containment design limit for internal vacuum of 0.5 psid. A vacuum relief line consists of a self-actuating vacuum relief valve, a pneumatically operated isolation valve, associated piping, and instrumentation and controls.

SEQUOYAH - UNIT 2 8 3/4 6-6 Amendment No.188

.

Person / Time
ML20087J323
Site:	Sequoyah (DPR-77-A-197, DPR-79-A-188)
Issue date:	04/28/1995
From:	Hebdon F NRC (Affiliation Not Assigned)
To:
Shared Package
ML20087J326	List: ML20087J323 ML20087J329
References
NUDOCS 9505080213
Download: ML20087J323 (24)
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