ML20147C284

Lic DPR-39 & DPR-48 Appl for Amend to Tech Specs Proposed Incorporating ECCS Flow Requirements Re a Blow Balance Test & tamper-proof Covers for Manual Throttle Valves

ML20147C284
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	10/05/1978
From:	Reed C COMMONWEALTH EDISON CO.
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 7810120036
Download: ML20147C284 (7)

Text

'

j f M( C mmonwsith Edison

- ) . One First National Plaza. Chicago, ininois D 7' Address Reply to: Post Office Box 767 i' / Chicago, Illinois 60690 October 5, 1978 Director of Nuclear Reactor Regulation U.S. ' Nuclear Regulatory Consnission Washington, D.C. 20555 ,

Subject:

Zion Station Units 1 and 2

. Proposed Amendment to Facility' Operating License Nos. DPR-39 and DPR-48 Incorporating ECCS Flow Rate Surveillances-NRC Docket Nos. 50-295 and 50-304

. References (a): July 18, 1977 letter from A. Schwencer-to R. L. Bolger. NRC. Docket Nos. 50-295 and 50-304 (b) : September if>, 1977 letter from D. E. O'Brien to A. Schwencer. NRC Docket Nos. 50-295 and t 50-304 t7~

(c): . September 8,1978 letter from William F.

Naughton to Director of-Nuclear Reactor Regulation, NRC. Docket Nos. 50-2f5 and 50-304 t

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Dear Sirs

~

Pursuant to 10 CFR 50.59 Commonwealth Edison Company hereby requests a change to Operating. License'Nos. DPR-39 and DPR-48, Appendix A, Technical Specifications, as specified in Attachment 1. The purpose of this amendment is to incorporate ECCS flow rate surveillance requirements in the Zion Station Technical Specifications per the NRC Staff's requests of Reference (a) .

In response to the NRC Staff requests of Reference (a), Commonwealth Edison informed the NRC Staff per Reference (b) that manual throttle valves are.used on both the HPSI and LPSI systems'at Zion Station and that during the upcoming refueling outages an ECCS flow balance test would be performed on each unit. In addition,' Commonwealth Edison indicated

~ that following these testof tamper-proof covers would be installed over each of,thelvalves. 1Per Referenco-(c),

. Commonwealth Edison indicated to the NRC that the flow verification tests had been performed and that tamper-proof

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- . covers;hadsbeen, installed over'ench' of the valves following these '

L' test's'. " Reference ? (c) _. also ' indicated that Comunonwealth Edison' *had

• performed additionaltinvestigations to' determine 'acceptablej

' toleranceson ECCS.flowsTsinc~ e the[ design flows.specifici'in the i tZion' Final ~ Safety"AnalysistReportfwere single values?with'no;

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.y uncertainties included. c Based (on Lthese , investigations, . Cossaonwealth ' .

~ Edison concluded'thatfaL15% tolerance'on:ECCS flows was acceptable

< 'and that'the BCCS flow rates-lfromI the' Zion' Unit 1 and'2? tests ~ fell?

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'The.purpo.wselof.this. proposed change is!to provihel.. ,

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surveillance. requirements that assure, proper ECCS' flows'will be- "

' maintained in.the event.of a LOCA. Maintenance'of proper flow' .

resistance'and: pressure drop;in

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the pipingisystem toeach injection ,

spointiis necessaryjtos. ~i , _

4 e (1) Preventi totallpump flowf frcun [ exceeding. runout 4 L

[ 2 conditions when ;the1 system is . in' its ' minienna resistanee configurationsy' V .'

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.(2) Provide Lthe proper flow split between? inIebtion.

points in"accordance with the assumptions used in,

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the ECCS-LOCA analysesr"and >

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'(3) Pr ide an' acce$ table level of' total ECCS flow to . ,

Lall" injection points equal to or above;that as'sumed r -in the BCCS-LOCA analyses.- *

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'The< proposed technical specific'ati,ons in Attachment 1 y havefbeen' reviewed by comanonwealth Edison.On-Site.and Off Site , -

Review with the conclusion'that.there are no unreviewed safety. ,

questions. o

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. Pursuant.to 10.CFR 170, Casumonwealth Edison has determined that this: proposed amendment'is.a combined. class II.and.. Class I' Amendment. 'As such, Comanonwealth Edison'has enclos'ed;a fee,re-- ,

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h ;mittanceiin the amount ~ of: $1',600.00 for.this proposed'~smondment. '

The basis for this fee'~determinationjis:that the proposed l changes., .

> are prisaarily administrative in that the" proposed change Lin- '

3 corporates surveillance requirements of setpoints previouslyl,re-

' viewed,and approved by the ~NRC Staff. -

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i ZION STATION UNITS 1 AND 2 NRC DOCKET ~NOS. 50-295'AND 50-304 ATTACHMENT 1 r

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t LLIMITING CONDITION.FDR OPERATION -SURVEILLANCE REQUIREMENT

~

I [3.8.3 .D. If these conditions cannot be met 4.8.3 D. Not Applicable 4

1 the reactor shall be brought to the

- hot shutdown condition within four '

s

! hours. After a maximum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

] in the hot shutdown condition, if the ,

syutem is not operable the reactor shall be brought to the cold shutdown 4 condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

t.

4. System testing of centrifugal charging, 4.- System testing of centrifugal charging,..

j. safety injection, and residual heat safety injection, and residual heat removal' pump systems.- removal pump systems.

A system test shall be' performed f A.- A system test shall.be performed 'A.

.by manually initiating the safety at each refueling outage. The

-injection signal to initiate test shall:be considered

operation of the centrifugal satisfactory if control board charging, safety injection, and indication and visual observa-residual heat removal pump systems. tions indicate that.all

com-i The centrifugal. charging and safety- ponents,.as plant: conditions

, injection pumps shall'be. blocked- allow, have received.the safety

, from starting during the test. If injection signal and-operated one of two residual heat removal - satisfactorily.

pumps is not operating, it shall be blocked from starting the test.. B. Proper valve steet position shall be verified within'4 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

h. Proper E.C.C.S. injection flows :following the completion of will be maintained by verifying stroking or maintenance which-valve-stem positions and performing may affect 1 the position of the flow balance' tests. . following throttle valves when they are required operable:

l l

SI8810A, B, C, D ,

SI9003A, B, C,2D 173 ~ SI9013A, B,C,D _

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. LIMITING CONDITION R)R CPERATION SURVEILLANCE REQUIRDIENT 4.8.4.B A flow balance test shall be per-formed on the affected lines during the next refueling outage following '

valve stroking or maintenance or other system modifications which might alter the E.C.C.S. flow characteristics.

E.C.C.S. flow rates for single pump operation shall meet the following requirements under the minimum resistance configuration:

1. Charging pump cold leg injection plus seal injection shall not' exceed 550 GPM; 1

2. SI pump hot or cold leg injection plus mini-flow shall not exceed 650 GPM;

3. The minimum charging pump cold leg injection through any 3 lines shall be 265 GPM; and

4. The minimum SI pump cold leg injection through any 3 lines shall be 432 GPM.

'173A l

s

I Basis:

4.8 Complete Energency Core Cooling Systems The "Recircualtion Sump to RHR Pump Isolation l

- tests cann:M: be performed when the re- Valves" are stroked at a test pressure of '

. actor is operating because a safety 20 psig to simulate post loss-of-coolant

injection nignal causes reactor trip, accident conditions. The valves are used sain feedwater isolation and containment during the recirculation phase approximately '

isolation. The method of assuring 30 minutes after the accident. 'At this time operability of these systems is therefore, the contairement pressure is 'less than 20 psig. ' i to ecebine systems tests to be performed during unit refueling shutdowns, with more The purpose of these surveillance requirements j frequent component tests, which can be per- is to provide assurance that proper E.C.C.S.

! formed during reactor operation. flows will be maintained in the event of a LOCA. Maintenance of proper. flow resistance

The refueling outage systems tests and pressure drop in the piping system to demonstrate proper automatic operation of each injection point'is necessary to

(1) the Emergency Core Cooling Systems. With prevent total pump flow from exceeding runout the pumps blocked-from starting a test conditions when the system is in its minimum signal is applied to initiate automatic resistance configuration; (2) provide the

~

action and verification is made that the proper flow split between injection points components receive-the safety injection in accordance with the assumptions used in signal in the proper sequence. The test the ECCS-LOCA analyses; and (3) provide an demonstrates the operation of the valves, acceptable level of total ECCS flow to all pump circuit breakers, and automatic injection points. equal to or above that circuitry. ll) assumed in the ECCS-LOCA analyses.

The active components (pumps and valves) Accumulator check valve operability tests

' are to be tested monthly to verify that are conducted to ensure that, if required, the pumps are in satisfactory running the accumulators will discharge as designed order and that the valves are free to move. to the reactor coolant system. The leak The test interval of one month is based on tightness of the valves is also checked to the judgment that more frequent testing assure that the accumulators will not be would not significantly increase the re- overpressurized during operation.

liability (i.e., the probability that the component would operate when required), (1)FSAR Section 6.2 and would result in increased wear over a long period of time.

The valves are fully stroked each refueling outage to verify their operability for component isolation.

. 196

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