ML19309H459

Proposed Tech Specs 2.5 & 3.9,clarifying Requirements for Ensuring Availability of Auxiliary Feedwater During Plant Operation

ML19309H459
Person / Time
Site:	Fort Calhoun
Issue date:	05/12/1980
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML19309H452	List: ML19309H451 ML19309H456 ML19309H459
References
NUDOCS 8005130309
Download: ML19309H459 (4)

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2.0 LIMITII1G C0!TDITI0ils FOR OPEHATIOII I

i' 25 Steam and Feedwater Systems  ;

i Applicability  ;

• Applies to the operating status of the steam and feedwater systems.

i Objective i

To define'certain conditions of the steam and feedwater system necessary to assure adequate decay heat removal.

I S_oecifications i The reactor coolant shall not be heated about-3000F unless the following conditions are met:

i (1) Both auxiliary feedwater pumps are operable. One of the auxiliary feedvater pumps may be inoperable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

provided that the redundant component shall be tested to I demonstrate operability.  ;

i 4 (2) A minimum of 55,000 gallons of water in the emergency ,

feedwater storage tank and a backup water supply to the emergency feedwater storage tank from the Missouri River

, by the fire water system.

t (3) All valves, interlocks and piping associated with the above components required to function during accident conditions are operable. Manual valves that could inter-l rupt auxiliary feedwater flow to the steam generators

' shall be locked in the required position to ensure a i flow path to the steam generators.

l l (4) The main steam stop valves are operable and capable of j closing in four seconds or less under no-flow conditions.

, Basis i

A reactor shutdown from power requires a removal of core decay heat. Lmnediate decay heat removal requirements are normally l satisfied by the steam bypass to the condenser. Therefore, core decay heat can be continuously dissipated via the steam-

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bypass to the condenser as long as feedvater to the steam generator is available. Normally, the_ capability to supply feedwater to the steam generators is provided by operation In the unlikely event

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! of the turbine cycle feedvater system.

of complete loss of electrical power to the station,. decay heat removal is by steam discharge to the atmosphere via the main steam safety and atmospheric dump' valves. Either auxi-liary feedwater pump can supply sufficient feedvater for re-

' moval of decay heat from the plant. The minimum amount of water in the emergency feedwater storage tank is the amount _

.needed'for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.of such~ operation. The tank can be re-Lsupplied with water from the fire protection system.ll) 2-28 ATTACHMENT:A

3.0 SURVEILLAIICE REQUIREME?ITS 3.9 Auxiliary Feedvater System A1:plicability Applies to periodic testing requirements of the turbine-driven and motor-driven auxiliary feedwater pumps.

Objective To verify the operability of the auxiliary feedvater ( AFW) system and its ability to respond properly when required.

Specifications (1) The position t.f valves necessary to ensure auxiliary feedwater flow to the steam generators shall be verified by a monthly inspection. Anytime maintenance is per-formed on the auxiliary feedvater system which alters valve alignments, an operator shall check that the AFW system valves are properly aligned, to ensure AFW flow to the steam generators, and a second operator shall independently verify proper valve alignment.

(2) The operability of the motor-driven auxiliary feedwater pump, the steam turbine-driven auxiliary feedvater pump, and the auxiliary feedwater pumps' steam generator level regulating valves HCV-1107A, HCV-1107B, HCV-1108A, HCV-1108B, and auxiliary feedwnter cross-tie valve HCV-138h shall be confirmed at least every three months.

(3) The capabilities of the motor-driven and turbine-driven auxiliary feedwater pumps shall be verified by using local pressure indicators and flow indicators in the control room. The discharge pressure vill be verified to be 40 psig above the steam generator pressure at rated steam flow.

(4) Following cold shutdown and prior to raising the reactor coolant temperature above 3000F, the motor-driven auxi-liary feedwater pump chall be tested to verify the nor-mal flow path for auxiliary feedwater to the steam gener-ators.

Basis The valve position verifications performed monthly and follow-ing auxiliary feedvater system maintenance vill confirm the availability of an auxiliary feedwater flow path to the steam generators.

3-62 Change Ilo. 7 February 28, 1974 l

DISCUSSION The Omaha Public Power District received a letter from the Commission, dated October 22, 1979, requesting a broad spectrum of operational, administrative, and equipment changes to the auxiliary feedwater system. The proposed specifications revise specifications 2.5 and 3 9 in accordance with the recommendations GS-2 and GS-6, as specified in Enclosure 1, Sections 3.3.1.1 and 3.3 1 3 of the above letter. The proposed specifications are consistent with Combustion Engineering Standard Technical Specifi-cations. The proposed Technical Specifications do not involve significant hazards considerations or involve an unreviewed safety question for the following reasons:

(1) The proposed specification is strictly an administrative change and does not change, modify, or limit the oper-ational capability of the auxiliary feedwater system.

The proposed specification provides for a confirmatory check of the system's operability.

(2) Performance of the proposed surveillance is consistent with URC requirements and does not interfere with or introduce a new factor in the operation of safety grade systems not previously analyzed.

(3) Ho margins of safety, currently defined in any Technical Specification, are applicable to or related to the oper-ation of the auxiliary feedvater system.

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JUSTIFICATION FOR FEE CLASSIFICATION The proposed amendment in deemed to be Class II, within the meaning of 10 CFR 170.22, because it is administrative in nature and has no safety or environmental significance.

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