ML20004F941

Forwards Addl Concerns Re Containment Isolation & Leak Testing Per 810619 Telcon

ML20004F941
Person / Time
Site:	Fermi
Issue date:	06/23/1981
From:	Colbert W DETROIT EDISON CO.
To:	Kintner L Office of Nuclear Reactor Regulation
References
EF2-53867, NUDOCS 8106260314
Download: ML20004F941 (15)

Text

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M V as 3 3 (313) 237-8000 June 23, 1981 -

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M EF2 - 53867

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ffl Mr. L. L. Kintner

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Division of Project Management h')

p Office of. Nuclear Reactor Regulation

%c U. S. Nuclear Regulatory Commission Washington, D. C.

20555

Reference:

Enrico Fermi Atomic Power Plant, Unit 2 NRC Docket No. 50-341

Subject:

Additional Concerns Regarding Containment Isolation and Leak-Testing Statements from the Containment Systems Branch draft SER were given to us for resolution; they were labeled as CSB-1,

-2, and -3.

We discussed these statements with you and John' Lane (NRC) via tele-phone on June 19, 1981. During the telecon, Mr. Lane brought out the concerns which were the bases for the draft-SER statements.

The information attached responds to these concerns.

Sincerely, W. F. Colbert Technical Director Enrico Fermi 2 WFC/MLB/dk 00/

Attachment

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Attcchment to EF2-53867 Juna 23, 1981 4

I.

' Concerns on FSAR Statements Re Appendix J Testing In response to the NRC's questions concerning compliance of the Contain-ment Leakage Testing Program with the requirements of Appendix J to 10CFR Part 50, the following. revisions will be made to the FSAR:

Page 6.2 - 56o, Section 6.2.4.4.1, seventh paragraph, Acceptance Criteria, will be revised to read:

" Lam shall be no greater than Ld (where Ld is the design leakage rate at pressure Pa, as specified in the technical specifications), which conforms to the requirement of Appendix J to 10CFR50 that Las shall be less than 0.75 La (where La is the maximum allowable leakage at pressure Pa).

Note: See Table 6.2-1 for pressure and leakage values."

Page 6.2-71, Table 6.2-1, Part I, General Information, will be revised to read:

"Drywell Torus A.

De' sign pressure, Pa, psig 56 56 B.

Maximum allowable pressure, psig 62 62 C.

Design temperature, F

281 281 D.

Free Volume, eu ft 163,730 130,900 E.

Design leak rate, Ld, %/ day 0.5 0.5 F.

Maximum allowable leak rate, La,

%/ day 1

NA" Page 6.2-56p, Section 6.224.4.2, third paragraph, second sentence, will be revised to read:

" Air locks shall be tested -at 6-month intervals. However, air locks which are opened during such intervals shall be tested'after each opening."

Page 6.2-56p, Section 6.2.4.4.3, fourth paragraph, first sentence, will be revised to read:

"The tests shall be performed by local pressurization applied in the same direction'that the valve would be required to perform its safety function, unless it has been determined that applying the pressure in the opposite direction will provide equal or more conservative results.

(Manufacturer's te*t data verifying that the results will be equal or more conservative will be available at the Enrico Fermi 2 plant for review.)"

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II.

Additional Information for Bypass Leakage Paths Tested by Section*XI Containment

• Actuator Isolation Quality Leakage Test Valve-Type Signal Group Interval Criteria V17-2036 Solenoid B, K B

Refueling i gpa V17-2037 Solenoid.

B, K B

Refueling i gym V17-iO24 Solenoid B, K B

Refueling 1 gpm

-V17-2025 Solenoid B, K B

Refueling 1 gym V8-2198 Motor B. K B

Refueling i gpm

.V8-2200 Motor BK B

Refueling i gpa V8-2232 Motor B

B Refueling 1 gpm

• Signal B = vessel level 2 Sig'nal'K = high drywell pressure All valves are operable from the control room and have position indication in the control room.

III.

Justification for Classification of Drywell Atmosphere Sample Lines 02/H2 analyzers are required and considered to be essential per II.F.1 of NUREG-0737;.i.e. we cannot meet.1/2 hour' requirement without operating the instruments continuously.

IV.-

Justification for Single Isolation Signal on RWCU Inlet High.drywell pressure is omitted as an isolation signal to avoid inadvertent isolation which may result in reactor coolant chemistry problems and RPV bottom head thermal problems during small leak or small break accidents.

The system isolates on:

1.

Reactor Vessel Low Level 2 2.

RWCU Space Temperature High 3.

RWCU Inlet Line High Flow 4.

RWCU Space High Differential Temperature All these signals are Class 1E.

The RWCU valves also close on initiation of SLCS.

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V.

Verify Containment and Accident Isolation Signals on MSIVs are Safety Grade Signal Safety Grade B

Reactor Vessel Level 2 Yes D

Main Stm Line Hi Rad Yes E

Main Sem Line Hi Flo Yes F

Main Stm Line Tunnel Hi Temp Yes

.F

. Main Stm Line Tunnel Hi Temp Yes G

Main Sem Line Low Press Yes J

Low Condenser Vac Yes P

Turbine Bldg Hi Temp Yes G. J, and P sensors are located in non-seismic turbine building VI.

Classification of Five Valves in EF2-53694

_alve Classification V

Penetration Line X-23Bb Drywell Pressure V5 - 2546 Essential X-29Bc Drywell Pressure V5 - 2547 Essential X-47a Drywell Pressure V5 - 2548 Essential X-47b Drywell Pressure V5 - 2549 Essential X-47c PCMS/Drywell Instrumentation V5 - 2230 Essential VII.

-Verification of Essential Classification on Certain Systems in Appendix H Table II.E.4.2-1 Penetrations I 22 and 36 are pneumatic supply lines which are not essential and are isolated.by High Drywell Pressure and Low Level 2.

In order to use the safety relief valves for long term shutdown cooling, we have provided a keylock switch for bypassing the isolation.

-Penetrations 39 A&B are not essential lines and cre isolated on High Drywell Pressure and Low Level 2.

A keylock is providad to bypass the isolation sig-nals to allow activat~ an of the containment sprays.

VIII. Isolation Signals on Recire Pump Seal Purge Lines We agree that the EECW supply to recire pump seals is sufficient to protect the seals and hr.ve initiated a design change to isolate the Seal Purge Lines on High Drywell Pressure or Low Level 2.

IX.

Corrections to Table of Exceptions to Appendix J Item 4 in our letter to the NRC, EF2-53498, June 9,1981, was a Table of Exceptions to Appendix J.

Mr. Lane noted some inaccuracies in this table and also in Table 6.2-2 in the FSAR. In response to these questions, the Table of Exceptions has been reviewed and revised. The revised table is attached.

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Table 6.2-2, pages 4 and 5, penetrations X-13A, 133, 16A, and 16B will be

. revised in the case of the inboard isolation valves by changing the Type C test column entry from "no" to "yes" and deleting " Note 27" from the Remarks column.

(Penetration X-13A, 13B, 16A, and 16B should be deleted from the i

Table of Exceptions to 10CFR50, Appendix J, that was sent to the NRC on June 9, 1981.)

Tabl'e 6.2-2, page 34, will be revised by deleting " Note 27."

(Notes 9 and 10 should be del _ted frcm the Table of Exceptions to 10CFR50, Appendix J, that was sent to the NRC on June 9, 1981.)

Table 6.2-2, pages 11a and 12, penetrations X-39A and 39B will be revised in the case of the inboard isolation valves by adding " Note 3" to the

'~ ~ Remarks column.

(" Note 3" should be added to the Exception column aad

" Note 4" to.the Justification column for penetrations X-39A and 395 in the Table of Exceptions to 10CFR50, Appendix J, that was sent to the NRC on June 9, 1981.)

.X.

Design of Piping and Valves Required for Isolation We refer the NRC to FSAR Sections 6.2.4.2.1 and 7.3.2 for discussions of design requirements of components necessary for isolation.

Basically, all isolation valves are quality group A or B, the line between the isolation valves is quality group B or better, closed loops are quality group B, and all isolation valves with operators are controlled from the Control Room and have position indication of open and closed.

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R: vised 6/19/81 I

TARLE - EXCEPTIONS TO 10CFH50_ APPENDIX'.I Pene trat ion Valve 4

Number-System Title' Numbe r Exception Justification X-7A Main Steam Line A V17-2003 Hote 1 Note 2 X-7B Hain Steam Line B V17-2001 Notet I Note 2 l'

X-7C Main Steam Line C V17-2002 Notr 1 Note 2 i

X-7D Main Steam Line D V17-2004 Note 1 Note 2 1

X-8 Main Steam Line Drains V17-2009 Note 3, Note 4 _.

X-10 Steam to RCIC Turblra V17-2030 Note 3 Note 4 7

X-Il Steam to HPCI Turbine V!7-2020 Note 3 Note 4 l

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I X-15 Combustible Gas Control V4-2144 Note 5 Note 4.

System Suction l

i X-17 RHR Discharge to Head Spray V8-2172 Note 3 Note 4 1

X-22 Nitrogen to Drywell V4-2080 Note i Note 2 l

X-13 Reactor Building Closed V8-2485 Note 3 Note 4 Cooling Water Supply i

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TABLE - EXCEPTIONS TO 10CFR50 APPENiliX.I

-Penetration

Valve Number System Title Numbe r l Exception Justifiention X-24 Reactor Building Closed V8-3890 &

Note 3 N.ite 4 Cooling Water V8-2486 X-25 Drywe11 Exhaust and' Air VR3-3024

. Note 5 Note 4

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Purge X-26 Drywell Air Purge-Inlet VR3-30ll Note'5 Note 4 X-27a~

Containment Atmosphere V5-2159 Note 6 Note 4 Sample

.X-27b

. Containment Atmosphere VS-2160 Note 6-Note 4'

. Sample X-27c Containment Atmosphere V5-2161

. Note 6

. Note 4 Sample X-27d Containment Atmosphere V5-2162 Note 6 Note 4 Sample X-27e Containment Atmosphere V5-2163 Note 6 Note 4 Sample X-27f Containment Atmosphere V5-2164 Note 6 Note 4 Sample X-29Aa Reactor Water Sample V17-2077 Note i Note 2 X-29Be Drywell Instrumentation V5-2231 Note 6 Note 4 X-318 Drywell On-Line Pressure VR3-2825 Note 1 Note 2 Control X-34A Reactor Building Closed V8.2484 Note 3 Note 4 Cooling Water.lupply

1 TABIA - EXCEPTIONS TO 10CFR50 APPENDIX.i Penetration

' Valve-Number System Title Number Exce:ption Justification X-348 Reactor. Building Closed

.V8-3889 &

Note 3 Note 4 i

Cooling Water Return V8-2483 4

X-36 Nitrogen to Drywell 1V4-2188 Note !

Note 2' l

X-39A RHR to Containment Spray V8-2169

1. Note 3

1. Note 4 Header

2. Note ll

2. Note 12

- X-398 RHH to Containment Spray V8-2170

. l. Note 3

1. Note 4-Header

2. Note 11

2. Note 12 i

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X-44 Combustible Cas Control-V4-2143 Note 5 Note 4 i

System Suction X-47e Drywell Pressure V5-2230 Note 6 Note 4

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X-48a Containment Atmosphere VS-2151 Note 6 Note 4 l

Sample X-48b Containment Atmosphere VS-2152 Note 6 Note 4

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Sampic X-48c Containment Atmosphere V5-2153-Note 6 Note 4 Sample X-48d Containment Atmosphere V5-2154 Note 6 Note 4 Sample X-48e Containment Atmosphere V5-2155 Note 6 Note 4 Sample X-48f Containment Atmosphere V5-2156,

Note.6 Note 4 Sample X-49a Recirc Pump Seal Purge V8-3767 &

Note 3 Note 4-V8-3710 t

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-TABLE - EXCEPTIONS TO'10CFH50 APPENDIX.I Penetration Valve..

Number' System Title Lum 6er.

Exceptico Justification X-Sla TRecirc rump Seal Purge V8-3768 &

' Note 3

' Note 4 V8-3590 X-204A Drywellito Torus Vacuum V4-2036 Note 1 Note 2 Breaker Nitrogen Supply X-204B Drywell to Torus Vacuum V4-2065 Note i Note 2 Breaker Nitrogen Supply f

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.X-204C Drywell'to Torus Vacuum V4-2075 Note i Note 2

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Breaker Nitrogen Supply 4

X-204D Drywell to Torus Vacuum V4-2077 Note 1 Note 2 Breaker Nitrogen' Supply X-204E Drywell to Torus Vacuum V4-2082 Note'l Note 2 Breaker Nitrogen Supply 1

X-204F Drywell to Torus Vacuum V4-2084 Note 1 Note 2 j.

Breaker Nitrogen Supply X-204G Drywell to Torus Vacuum V4-2086 Note 1 Note 2 Breaker Nitrogen Supply X-204H Drywell to Torus Vacuum

.V4-2088-Note 1 Note 2 Breaker Nitrogen Supply j

X-204J Drywell to Torus Vacuum V4-2090 Note 1 Note 2 Breaker Nitrogen Supply

>-204K Drywell to Torus Vacuum V4-2092 Note 1 Note 2 Breaker Nitrogen Supply X-204L Drywell to Torus Vacuum V4-2094 Note 1 Note 2 1

Breaker Nitrogen Supply 4

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- TABLE - EXCEPTIONS TO IOCFR50 APPEND [X.I

,I Valve Penetration

' Number

~ Exception Justification.

Number

. System Title X-204M Drywell to Torus Vacuum V4-2096 Note 1 Note:2-

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Breaker Nitrogen Supply 4

X-205A Torus to Secondary ~ Contain-v21-2015 Note 5 Note 4' ment Vacuum Breaker 4

X-2058 Toru's-to Sdcondary-Contain-

~V21-2016 Note 5

. Note'4 ment Vacuum Breaker i

X-205C Torus to Secondary Contain-

.VR3-3013 Note 5

' Note 4 ment Vacuum Breaker 7

X-205D Torus to Secondary Contain-VR3-3015 Note 5' Note 4'-

I' ment' Vacuum Breaker X-206A Torus Pressure and Liquid

.VS-2552 Note 3 Note 4

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Level Instrumentation 1

l X-206B Torus Pressure and Liquid V5-2553 1.; Note.13

1. Note 14

2. Note 3

.2. Note 4 i

Level Instrumentation X-206C Torus Pressure and Liqu'd-

'V5-2550 Note 3 Note 4 l

Level Instrumentation i

X-206D Torus Pressure and Liquid V5-2551

'l. Note 13

1. h' ate 14 t

l Level Instrumentation-

2. Note 3-

2. Note 4-X-206E Torus Pressure and Liquid

'V5-2555

1. Note 13' l'. Note 14 i

Level Instrumentation

2. Note 3

2. Note 4 j

X-206F Torus Pressure and Liquid V5-2556

1. Note 13.

1. Note 14' i

Level Instrumentation

2. Note 3

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TABLE - EXCEPTIONS To 10CPR50 APPE'mlX J A

Vilve Penetratica Number System Title Nonher Exce;ption Justification X-210A&8 RHR All penetra-

't. Note 13

1. Note 14 tion isola-

2. All valves

2. Note 4 or tion valves tes te:' ' i n the results'are I

reverse-conservative direction since test pres-sure tends to unseat the valve disk i

i X-211A RilR to Suppression Pool V8-2158 Note 1 Note 2 Spray I

X-211B RHR to Suppression Pool V8-2157 Note 1 Note 2 i.

Spray 4

X-212, 214,&

RCIC Turbine Exhaust Line Vil-2002 Note 1 Note 2-l 220 HPCI Turbine Exhaust Line V11-2006 Note 1 Note 2 RCIC Vacuum Breaker Line Vll-2026 Note 3 Note 4 HPCI Vacuum Breaker Line Vil-2019 Note 3 Note 4 X-213A&B Torus Water Management All penetra-

1. Note 13

1. Note 14 i

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2. All valves

2. Note 4 or tion. valves tested in the'results are reverse conservative.

direction since test pres-sure tends to unseat the valve j

disk i

X-215 Combustible Gas Control V4-2142 Note 5 Note 4 System i

X-215 Combustible cas control V5-2158 Note 6 Note 4 System i

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1 TABLE - EXCEPTIONS TO 10CFR50 APPEND [X'.I I-Penetration.

Valve Number Syst+m Title-Number Exce_ption Justification X-218 Combustible Gas Control

'V4-2140' Note 5 Note 4 System i

V4-2139' Note.5 Note 41 X-218 Combustible Gas Control System X-219 Combustible

• Gas Control V4-2141 Note 5 Note'4 System i

I X-219 Combustible' Cas Control V4-2166 Note 6 Note 4 System X-221 HPCI Turbine Exhaust Drain Vll-2008 Note 1 Note 2 X-222 RCIC Vacuum Pump Discharge V8-2235

' Note 1 Note:2 i

X-223A RHR Pump Suction All,penetra-

1. Note 13

1. Note'14 tion isola-

2. All valves 2.' Note 4 or the through D j

tion valves tested in results are reverse conservative direction since test pres-sure tenils to un-seat the relief valve.

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X-224A&B Core Spray Pump Suction All penetra-

1. Note 13 1.' Note.14

.2.

Note 3

2. Note.4-tion isota--

tion valves X-225 HPCI Pump Suction All penetra-

1. Note 13

1. Note 14' tion. isola-

2. Note 3

2. Note 4 tion valves X-226 RCIC Pump Suction All penetra-

1. Note 13.

1. Note 14 J

tion isola-

2. Note 3

2. Note 4 tion valves 1

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TABIE - EXCEPfl0NS 70 10CFR50 APPENillX.I

' Penetration Valva Number-System Title Numbe r

' Exception.

Just[fication X-227A&B Core Spray, Torus Water All_penetra-

1. Note 13l

1. Note 14 Management, HPCI, & RCic tion isota-

2. All valves

2. Note 4 or the tlon valves.

testeil in

~ results are reve rse conservative:

direction

'since test pres-sure tends to un-seat the' relief -

valve.

X-230 PCMS and Postaccident V5-2157 Note'6 Note 4' Atmosphere Sample Suetions X-231 PCMS and Postaccident V5-2165 Note 6 Note 4 Atmosphere Sample Suetions

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Notes:

1.

Globe valve tested in the reverse direction.

i 2.

The results obtained in this test configuration are conservat ive since test pressure tends to unscat. the valve disk.

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3.

~ Wedge-disk gate valve tested in the reverse direction.

4.

The results obtained in this : test configuration are equivalent to testing in the accident direction, since valves of this type have the same sealing characteristics in either direction.

5.

Butterfly valve tested in the reverse direction.

6.

Ball valve tested in the reverse direction.

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11.

Due to syst'm configuration the test pressure is not in the same j

direction as the. pressure existing when the. valve is required to perform its containment isolation function.

12.

The valve will-be tested in the correct direction during~the Type A tests.

13.

This valve will be Type C seat leak tested using water as the. test medium.

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.14.

The. flow path associated with:this penetration inside containment A

. terminates below the low water level in'the suppression pool.

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water seal is r.ssured during norma 1' plant operation and for more than-30 dayr. following an accident requiring containment-isolation.

It is not. credible that these isolation valves will he exposed to1 the containment. atmosphere at any time following the accident.

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