ML20153E648

Proposed Tech Specs on Limiting Condition for Operation Re Containment Isolation Valves

ML20153E648
Person / Time
Site:	Rancho Seco
Issue date:	08/31/1988
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20153E555	List: ML20153E551 ML20153E648
References
NUDOCS 8809060378
Download: ML20153E648 (4)

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i ATTACHMENT II ,

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TECHNICAL SPECIFICATIONS PAGES AFFECTED BY J

PROPOSED AMENDMENT NO. Ill, REV. 1. SUPPLEMENT 1 i

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.6-1 CONTAINMENT ISOLATION VALVES NORMAL (1) MAXIMUM AUTO OPERATING CLOSURE VALVE NUMBER DESCRIPTION 110L. POSITION TIME. sect SFV-22009 RC System Letdown AB Side YES OPEN 25 SFV-22023 RC System Letdown, RB Side YES OPEN 25 SFV-24004 RC Pump Seal Return, RB Side YES OPEN < 60 SFV-24013 RC Pump Seal Return, AB Side YES OPEN 12 SFV-46014 RB. CCH Supply, AB Side NO OPEN 14 SFV-46203 RB CCH Return, RB Side NO OPEN 14 SFV-46204 RB CCH Return, AB Side NO OPEN IB SFV-46906 CRD Cooling Hater. Supply, AB Side NO OPEN 13 SFV-46907 CRD Cooling Hater Return, RB Side NO OPEN 14 SFV-46908 CRD Cooling Hater Return, AB Side NO OPEN 11 SFV-53503 RB Purge Inlet, AB Side YES CLOSED (2) 25 SFV-53504 RB Purge Inlet, RB Side YES CLOSED (2) 25 SFV-53603 RB Press. Equalizer, RB Side YES CLOSED 25 SFV-53604 RB Purge Outlet, AB Side YES CLOSED (2) 25 SFV-53605 RB Purge Outlet, RB Side YES CLOSED (2) 25 SFV-53610 RB Press. Equalizer. AB Side YES CLOSED 25 SFV-53612 RB Atm. Purge Sample. AB Side YES OPEN 25 SFV-53613 RB Atm. Rad. Sample, AB Side YES OPEN 25 SFV-53615 Reactor Building Hydrogen Purge YES OPEN 25 SFV-53616 Reactor Building Hydrogen Purge YES OPEN 25 SFV-60001 RC System Vent Isol., RB Side YES OPEN 25 SFV-60002 RC System Vent Isol<. AB Side YES OPEN 25 SFV-60003 RC System Drain Isol., AB Side YES OPEN 25 SFV-60004 RC System Drain Isol., AB Side YES OPEN 25 SFV-66308 RB Normal Sump Drain, AB Side YES OPEN 25 SFV-66309 RB Normal Sump Drain, AB Side YES OPEN 25 SFV-70001 Przr. Liquid Sample Isol., RB Side YES CLOSED 25 SFV-70002 Przr. Liquid Sample Isol., AB Side YES CLOSE0 25 SFV-70003 Przr. Vapor Sample Isol., RB Side YES CLOSED 25 SFV-72501 Przr. Gas Sample Isol., RB Side YES CLOSED 25 SFV-72502 Przr. Gas Sample Isol., AB Side YES CLOSED 25 SFV-92520 Przr. Nitrogen Isol., AB Side YES CLOSED 25 (1) Valves without auto-isolation may be open provided the controls for the respective valve are attended by an operator. Auto-isolation valves may be in any position.

(2) See Section 3.6.7 1 Proposed Amendment No. 31, 72, 87, Ill, Rev. 1. Supp. I 3-40

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.6-1 (Continued)

CONTAINMENT ISOLATION VALVES NORMAL (1) HAY. MUM AUTO OPERATING CLOSURE yliVE NUMBER DESCRIPTION ISOL, POSITION IJJiL. m HV-20593 OTSG-A Sample Isol., AB Side NO CLOSED 12 HV-20594 OTSG-B Sample Isol., AB Side NO CLOSED 5 HV-20609 OTSG-A Blowdown Isol., RB Side NO CLOSED 15 HV-20610 OTSG-B Blowdown Isol., RB Side NO CLOSED 14 HV-20611 OSTGs Blowdown Isol., AB Side NO CLOSED 22 HV-53617 Reactor Building Hydrogen Purge NO CLOSED 25 HV-53618 Reactor Building Hydrogen Purge NO CLOSED 25 HV-70040 Hydrogen Monitor Containment .

Outlet Isol. NO CLOSED 25 HV-70041 Hydrogen Honitor Containment Inlet Isol. NO CLOSED 25 HV-70042 Hydrogen Honitor Containment Inlet Isol. NO CLOSED 25 HV-70043 Hydrogen Monitor Containment Outlet Isol. NO CLOSED 25 HV-70044 Hydrogen Monitor Containment

, Outlet Isol. NO CLOSED 25 HV-70045 Hydrogen Honitor Containment Inlet Isol. NO CLOSED 25

HV-70046 Hydrogen Monitor Containment Inlet Isol. NO CLOSED 25 HV-70047 Hydrogen Monitor Containment Outlet Isol. NO CLOSED 25

) (1) Valves without auto-isolation may be open provided the controls for the I i

respective valve are attended by an operator. Auto-isolation valves may be in any position.

1 l Proposed i

! Amendment No. Ill, Rev. 1, Supp. 1 )

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• RANCHO SECO UNIT 1 1ECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.6.7 The Reactor Building Purge Valves, SFV 53503, SFV 53504, SFV 53604, and SFV 53605, shall be closed with their respective breakers de-energized, except during cold shutdown or refueling. Valves SFV 53503 and SFV 53604 shall be verified to be in the above condition at least monthly. The breakers / disconnects on valves SFV 53504 and SFV 53605 shall be verified to be de-energized at least monthly.

! 3 6.S The Reactor Building Purge Valves shall isolate on high containment

radiation level. See Table 3.5.1-1 for operability requirements.

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7he reactor coolant system conditions of cold shutdown assure that no steam will be formed and hence no pressure buildup in the containment if the reactor coolant system ruptures, i The selected shutdown conditions are based on the type of activities that are being carried out and will preclude criticality in any occurrence.

The Reactor Building is designed for an internal pressure of 59 psig and an .

, external pressure 2.0 psi greater than the internal pressure. The design external pressure corresponds to the differential pressure that could be developed if the building is sealed with an internal temperature of 120'F with a >

barometric pressure of 29.0 inches of Hg and the building is subsequently cooled to an internal temperature of 80'F with a concurrent rise in barometric pressure to 31.0 inches of Hg.

When containment integrity is established, the limits of 10 CFR 100 will not be exceeded should the maximum hypothetical accident occur.

The OPERABILITY of the containment isolation ensures that the containment 1 i atmosphere will be isolated from the outside environment in the event of a i release of radioactive material to the containment atmosphere by l prassurization of the containment. Containment isolation within the time limits specified for valves which receive an automatic isolation signal ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for LOCA. Valves which are permitted to be open during plant operation are either part of closed systems which would not cause releases to the environment, or are administrative 1y controlled to ensure their rapid closure in the event of an accident. '

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Specifications 3.6.7 and 3.6.8 are in response to NUREG 0737 item II.E.4.2.

REFERENCE i

! (1) USAR, section 5 4 Proposed j

Amendment No. 31, 49, 87, Ill, Rev. 1. Supp. 1 3-40b