ML18192A608

In Reference IE Bulletin 78-02, Reviewed Equipment for Nuclear Steam Supply System Being Supplied by Combustion Engineering & Noticed That No Terminal Blocks in Exposed Locations That Perform Safety Functions in or Out of Containment

ML18192A608
Person / Time
Site:	Palo Verde
Issue date:	02/24/1978
From:	Van Brunt E Arizona Public Service Co
To:	Engelken R NRC/RGN-V
References
ANPP-10391-JMA/MFH, IEB-78-002
Download: ML18192A608 (10)

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P. O BOX 2I666 February 24, 1978 ANPP-10391-JMA/MFH PHOENIXs ARIZONA 65036

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Mr. R.

H. Engelken, Director U.

S. Nuclear Regulatory Commission Region V

202 Walnut Creek Plaza 1990 North California Boulevard Walnut Creek, California 94596

Subject:

NRC IE Bulletin 78-02, dated January 30, 1978 File:

D.4.06.1 78-005-206

Dear Mr. Engelken:

In reference to your IE Bulletin 78-02, which discussed failures of unprotected Marathon M-6012 Terminal Blocks when exposed to a simulated LOCA environmental condition, we have completed a review to determine if the concern identified will be present at PVNGS.

We have reviewed the balance of plant equipment at PVNGS for unprotected terminal blocks.

Terminal blocks for instrument and control cables will use NEMA type 12 enclosures.

This encLosure provides protection from direct water and chemical spray.

" Safety related terminal blocks used in the reactor protection system and engineered safety feature actuation system and which are required to operate in the post accident environment will be qualified per IEEE-323-1974.

Qualifying documentation for these terminal blocks will be submitted to the NRC later under the request made by John F. Stolz in his September 14, 1977 letter to Arizona Public Service Company on "Environmental Qualification Methodology."

Ãe have reviewed our equipment for the Nuclear Steam Supply System being supplied by Combustion Engineering and there are no terminal blocks in exposed locations that perform safety functions in or out of the contain-ment.

Environmental Qualification details on CE equipment are given in CESSAR.

We feel that the review of our terminal blocks and our plans for environ-mentally qualifying the terminal blocks will adequately identify and re-solve the problems identified in this bulletin.

EEVBJr/bJFH/mw Very truly yours, l/

Vice President Construction Projects ANPP Project Director,

Mr. R.

H. Engelken, Director USNRC - Region V

ANPP-10391-JMA/MFH Page 2

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B. Karner S.

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T. Barrow, Jr.

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C. Sterling R.

L. Rutkowski J

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~ SUCC 1 WD1THINDTOH 4TfD4 N CTS Mr. R. H. Engelken, Director Office of Inspection and Enforcement Region V

U. S. Nuclear Regulatory Commission 1990 N. California Boulevard Walnut Creek Plaza, Suite 202 Walnut, Creek, California 94596 Be:

Docket No. 50-275 Docket No.

50'323

Dear Mr. Engelken:

This is in response to your letter dated Janu-ary 30, 1978, enclosing IE Bulletin No. 78-02 which re-cpxested information concerning Terminal Block Qualifica-tion.

No unprotected terminal blocks are used in the Diablo Canyon Units for systems which must. function in the post-accident environment.

Very truly yours,

C.

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J. H. ORAKE vIcc mmcslocHm Soufhern California Edison Company R O. BOX 800 2244 WALNUTGROVE AVENUE ROSEHEAD, CALIFORNIA9I770 March 3, 1978 TCLCPSIOISE 2I3 572 2258 U. S. Nuclear Regulatory Commission Region V

Suite 202, Walnut Creek Plaza 1990 N. California Boulevard Walnut Creek, California 94596 Attention:

Mr. R. H. Engelken, Director Gentlemen:

7 PKil96I WR 31978 REGION'l V It6? ECTION) 4 EHfOKE!<Et'ubject:

IE Bulletin 78-02 Docket Nos.

50-361 and 50-362 San Onofre Nuclear Generating Station Units 2 and 3

Your letter of January 30, 1978 transmitted IE Bulletin 78-02 "Terminal Block Qualification".

Identified th'erein were potential problems associated with failures of unprotected terminal blocks utilized inside containment that were exposed to LOCA test environments.

The following responses are keyed to the question numbers in the bulletin:

Item 1 1.

Determine whether o'r not unprotected terminal blocks are used in your facility in systems which must function in the post-accident environment.

~Res esse Our investigation revealed that there are no unprotected terminal blocks inside containment to be utilized at San Onofre Units 2 and 3 in systems required to function in the post LOCA accident environment.

Terminal blocks are installed inside termination enclosures or boxes, or within equipment enclosures or cabinets.

Thus, all terminal blocks are installed within protective enclosures as a standard project design practice providing an assurance that no terminal blocks will be installed unprotected.

Items 2 and 3

2. If such terminal blocks are used, identify the systems involved and provide the documentation which demonstrates that these terminal blocks have been environmentally qualified; and

Mr. R. H. Engelken Page 2

March 3, 1978

3. If documentation is not available, provide your plans and schedule for achieving full qualification of affected circuits.

~Res onse Based on our response to Item 1 above, these items are not applicable.

Our response regarding Docket No. 50-206 was previously submitted under separate cover.

If you have any questions or require further cia~~ ication, please contact me.

Very truly,yours, cc:

U.S. Office of Inspection

& Enforcem nt Division of Reactor Construction Inspection Mashington, D.C.

20555

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Washington Public Power Supply System A JOINT OPERATING AGENCY P. 0. BOX 988 3000 GXO. WASHINCTON WAY RICHI.ANO, WASHINCTON 99352 PHONC (509) 375 5000 March 3, 1978

, Gol 170 Nuclear Regulatory Commission Region V

Suite 202, Walnut Creek Plaza 1990 N. California Boulevard Malnut Creek, CA 94596 Attention:

Nr.

R.

H. Engelken Director

Subject:

MPPSS NUCLEAR PROJECT NO.

1 IE BULLETIN NO. 78-02 DOCKET NUflBER 50-460

Reference:

Letter, R.

H. Engelken to N. 0. Strand, January 30, 1978.

Same Sub'p

Dear Nr. Engelken:

The referenced letter transmitted IE Bulletin 78-02 concerning unprotected terminal blocks used inside containment.

In response to this direction, the Supply System directed the Architect/

Engineer to review the subject IE Bulletin and determine the impact to MNP-1/4 equipment and design.

The Architect/Engineer has determined the following:

l.

Unprotected terminal blocks are not used in these facilities in systems which must function in the post accident environment.

2.

Protection for terminal blocks in such environments is provided by enclosures which are NEHA 12 or better.

The above information supports our compliance with IE Bulletin 78-02.

Very truly yours, ao<6 M~

D. L.

RENBERGEP, Assistant Director Generation

5. Technology DLR:JR:ct cc:

ter.

C.

R. Bryant, Bonneville Power Administration NRC, Office of Inspection and Enforcement (Mashington.D.C.)

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WashIngton Public Power Supply System A JOINT OPERATING AGENCY P. 0, BOX 950 3000 GEO, WACHINCTON WAr AICHI.ANO. WACHINC'fON 99352 PHON C (509) 375.5000 March 3, 1978 G02-78-84 Nuclear Regulatory Commission Region V

Suite 202, Walnut Creek Plaza 1990 N. California Boulevard Walnut Creek, CA 94596 Attention:

Hr.'.

H: Engelken Director (Q

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C

Subject:

WPPSS NUCLEAR PROJECT NO.

2 IE BULLETIN NO. 78-02 DOCKET NO. 50-397

Reference:

Letter, R.

H. Engelken to N. 0. Strand, Same Subject, January 30, 1978.

Dear Hr. Engelken:

The reference letter transmitted the subject IE Bulletin.

In response to the questions asked in IE Bulletin No. 78-02, our AE reports that there are no unprotected terminal blocks used in WNP-2 in systems which must function in the post-accident environirent.

The above information supports our compliance with IE Bulletin, 78-02.

Yery truly yours, DLR:GLC:ct D. L.

RENBERGER

, Assistant Director Generation

& Technology cc:

ter.

D.

Roe, Bonneville Power Administration NRC, Office of Inspection and Enforcement (Washington D.C.)