ML20212D583

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Proposed Tech Specs,Revising Section 3.6, Core Cooling Sys
ML20212D583
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 12/17/1986
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20212D581 List:
References
NUDOCS 8701020097
Download: ML20212D583 (6)
v • d • e


Text

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bb y (K 9H- ,r ' 13.6i CORE COOLING SYSTEMS C

[1 w Aamlip.ahility: Applies to the operating status of the core cooling lu . . systems. -

h To define those limiting conditions for operation that are

. necessary to insure operability of the core cooling n < ,

= system.

Sancifications A) The reactor shall not be critical unless the following conditions are met h' ,t 1) DMillE h , All of the pumps associated with at least one of p the two trains of emergency core cooling equipment must be operable. The pumps 1 .

associated with each train of emergency core

( cooling equipment are the followings

a. One high pressure safety injection pump rated at 1750 gpm at a head of 2250 feet.
b. One charging pump rated at 360 gpm at a pressure of 2300 psig. j

.[ c. One low pressure safety injection (core I t deluge) pump rated at 5300 gpm at a head of 390 feet. 9

+ d. One residual heat removal (IIHR) pump '

"p . rated at 2200 gpm at a total head of 300 feet.

L 2) At least one of two residual heat exchangers operable.

3) System valves and Interlocks required for p proper operation of core cooling systems operable.

p-B) The following valves and their operators will be

!- positioned as below and verified once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s: l YALVE NO. LOCATION ACTION RH-FCV-602 RilR heat Valve locked in closed exchanger position, Air supply bypass line lsolated whenever reactor critical and coolant temperature

> 3500F.

Ril-FCV-796 IlllR heat Valves blocked in exchanger throttled position, Air discharge supply isolated when-g10g{

p gg7 pg3 line ever reactor critical and coolant temper-ature > 3500F, 3-10

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l- This specification' assures that adequate emergency core cooling capacity is o available whenever the reactor is critical. Based on the loss of coolent analysis, melting of the cladding is prevented with only one high pressure safety injection pump. and one low pressure safety injection (core deluge) pump in operation. -

- Additionally, during the post-LOCA recirculation phase, sufficient cooling exists with only one charging, one HP51, and one RHR available. Each of the two trains of emergency core cooling equipment includes these two pumps. With the pumps associated with both trains of emergency core cooling equipment operable, substantial mar are available. With

. gin only exists one whenever diesel generator normaloperating power supplies or bothassociated and the pumps diesel generators with that diesel operable as required in item (2) of Specification 3.12, the high

. pressure safety injection pump and the low pressure safety injection pump would be started automatically. When the safety injection pumps are operating on off-site

. power, the charging pump would be started automatically. The RHR pumps would be available for manual start for long-term recirculation cooling.

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- As described in Reference 3, the RC5 OPS, in conjunction with administrative controls, prevents exceeding the temperature and pressure limits in Specification 3.4 while RC5 temperature is under 3400F or the RCS is not vented. Part C establishing limiting condition for operation regarding the disabling of the HPSI pumps to further assure that a pressure transient is not initiated. Part D establishes requirements regarding the disabling of a charging pump to assure that a pressure transient is not initiated while retalning the flexibility to establish, under strict administrative controls, a redundant emergency boration path should such action be necessary.

FCV-796 is required to be throttled open within the range specified in and for the ,

reasons sited within Reference (6). That throttled position has been determined by separate analyses to insure acceptable core performance during post-LOCA recirculation.-

REFERENCE:

(2) FDSA Section 5.2.8 (3) D.C. Switzer (CYAPCO) letter to D.L. :lemann (NRC),

dated May 22,1978.

(4) D.C. Switzer (CYAPCO) letter to D.L. Ziemann (NRC),

dated May 24,1978.

(3) D.C. Switzer (CYAPCO) letter to A. Schwencer (NRC),

dated September 7,1977.

(6) E.3, Mroczka (CYAPCO) letter to C.I. Grimes (NRC), dated December 17,1986. l 3-10h c

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