NRC Generic Letter 1987-03

NRC Generic Letter 1987-003: Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, Unresolved Safety Issue (USI) A-46

ML031140317
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Washington Public Power Supply System, Shoreham, Satsop, Trojan, Clinch River
Issue date:	02/27/1987
From:	Harold Denton Office of Nuclear Reactor Regulation
To:
References
USI A-46 GL-87-003, NUDOCS 8703060307
Download: ML031140317 (6)

UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D. C. 20555

'FEB 2 7 1987 TO: -All Licensees, Applicants and Holders of Operating Licenses Not Required to be Reviewed for Seismic Adequacy of Equipment Under the Provisions of USI A-46, "Seismic -Qualification of Equipment:in Operating Plants"

GENTLEMEN:-'

SUBJECT: VERIFICATION OF SEISMIC ADEQUACY OF MECHANICAL AND

ELECTRICAL EQUIPMENT IN OPERATING REACTORS, UNRESOLVED

SAFETY ISSUE (USI) A-46 (Generic Letter 87-03)

As a result of the technical resolution of USI A-46, "9Seismic Qualification of Equipment in Operating Plants," the NRC has concluded that the seismic adequacy of certain equipment in those operating nuclear power plants which have not previously been reviewed to current licensing requirements for seismic qualification must be reviewed to seismic criteria defined in the USI A-46 technical resolution. The USI A-46 developed procedures make use of earthquake experience data supplemented by test data to verify the seismic capability of equipment below specified earthquake motion bounds. In the staff's K

Judgment, this approach is the most reasonable and cost-effective means of ensuring that tWe purpose df GeneraT DesignCriteFTon-7 (10 Cr Part Du- -

Appendix A) is met for these plants.

Because affected plants are being asked to carry out this evaluation against criteria not used to establish the design basis of the facility, this resolution is a backfit under 10 CFR 50.109. The backfit analysis and -t findings may be found in the USI A-46 Regulatory Analysis (NUREG 1211) at pp. 31.

We have documented evidence in staff SERs that your plant either has been, I

or is required to be, reviewed to current licensing requirements for Seismic Qualification of Equipment (i.e., SRP-3.10, IEEE-344/75 and Regulatory Guide 1.100) and therefore you are inot required to respond to this letter or to perform the plant reviews described in the enclosures.

The information developed in resolving USI A-46 is described in the enclosures to this letter and is being provided to you for information only.

We would also like to call to your attention several recent incidents reported in Licensee Event Reports (LERs) which involved inadequate or missing anchorage.

Between late March 1986 and May 1986, three LERs were received that documented inadequate seismic anchorage of electrical equipment in operating nuclear power plants. The initial case was at the Davis-Besse 1 plant (LER 86-011)

where cabinet doors on Cyberex Class 1E equipment for essential instrument 120

aLTI5

, 870C

CARtD

of ao:o oc'53

p0

-2- YAC power were found to lack the required door bolts. The second LER concerned emergency diesel generator switchgear cabinets at the Cooper plant that were not fastened to embedded channels beneath the cabinets (LER 86-009). The third deficiency was found at the Dresden 2 and 3 plants, where it was determined that the control room control panels did not have positive anchorage to the floor (LER 86-009). In each instance, the deficiency had existed since plant construction and was the-result of Installation errors, since the design drawings had specified seismic anchorage.. As a consequence of these events, a review was initiated by the NRC Office for Analysis and Evaluation of Operational Data (AEOD). This review included an LER search which revealed four other instances of inadequate seismic anchorage or support of safety

1 related electrical equipment plus other related seismic inadequacies.

I

We are enclosing the regulatory a'naysis (NURE& 1211) and the USI A-46 technical findings (NUREG1030) for your information. The generic letter, which was issued to each nuclear plant that is required to perform seismic adequacy reviews under the provisions of USI A-46, is included as Appendix A

to NUREG-1211;

Sincerely, A

T

.. , I

L II

Harold R. Denton, Di Office ul ear_2R RegulationI

Enclosures:

L NUREG 1211;

2. NUREG 1030

. I -. . i.

cc: Service List':i k ,.I

I

I

I .

. I

. r.

_ _, A

LIST OF RECENTLY ISSUED GENERIC LETTERS ' i "

Generic Date of Letter No. Subject I ssuance Issued To GL 87-02 - VERIFICATION OF SEISMIC 02/19/87 ALL HOLDERS OF

ADEQUACY OF MECHANICAL AND OPERATING

', ,I

ELECTRICAL EQUIPMENT IN LICENSES NOT

OPERATING REACTORS CUSI A-46) REVIEWED TO

CURRENT

LICENSING

CRITERIA ON

4A '

SEISMIC

QUALIFICATION

OF EQUIPMENT

GL 87-01 PUBLIC AVAILABILITY OF THE NRC 01/08/87 ALL POWER

OPERATOR LICENSING EXAMINATION REACTOR

QUESTION BANK LICENSEES AND

APPLICANTS FOR

AN OPERATING

LICENSE

GL 86-17 AVAILABILITY OF NUREG-11699 1017/m6 ALL LICENSEES - 4-

"TECHNICAL FINDINGS RELATED TO OF BOILING .

GENERIC ISSUE C-B WATER REACTORS  : -,.

BWR MSIC LEAKAGE AND LEAKAGE I-'

CONTROL SYSTEM

GL 86-16 WESTINGHOUSE ECCS EVALUATION 10/22/e6 ALL

MODELS PRESSURIZED

WATER REACTOR

APPLICANTS AND

LICENSEES

GL 66-15 INFORMATION RELATING TO ALL LICENSEES.

COMPLIANCE WITH 10 CFR 50.49, AND HOLDERS OF

"EQ OF ELECTRICAL EQUIPMENT AN APPLICATION

IMPORTANI TO SAFETY" FOR AN

OPERATING

LICENSE *

GL 86-14 OPERATOR LICENSING 08/20/86 ALL POWER -- F

EXAMINATIONS REACTOR

LICENSEES AND-

APPLICANTS

GL 86-13 POTENTIAL INCONSISTENCY 07/23/86 ALL POWER

BETWEEN PLANT SAFETY ANALYSES REACTOR

AND TECHNICAL SPECIFICATIONS LICENSEES WITH

CE AND B&W

PRESSURIZED

WATER REACTORS

6L 86-12 CRITERIA FOR UNIQUE

PURPOSE

07/03/e6 ALL NON-POWER

EXEMPTION FROM CONVERSION FROM REACTOR

THE USE OF HEU FUEL LICENSEES

AUTHORIZED TO

USE HEU FUEL

VAC power were found to lack the required door bolts. The second LER concerned emergency diesel generator switchgear cabinets at the Cooper plant that were not fastened to embedded channels beneath the cabinets (LER 86-009). The third deficiency was found at the Dresden 2 and 3 plants, where it was determined that the control room control panels did not have positive anchorage to the floor (LER 86-009). In each Instance, the deficiency had existed since plant construction and was the result of installation errors, since the design drawings had specified seismic anchorage. As a consequence of these events, a review was initiated by the NRC Office for Analysis and Evaluation of Operational Data (AEOD). This review included an LER search which revealed four other instances of inadequate seismic anchorage or support of safety related electrical equipment plus other related seismic inadequacies.

We are enclosing the regulatory analysis (NUREG 1211) and the USI A-46 technical findings (NUREG 1030) for your information. The generic letter, which was issued to each nuclear plant that is required to perform seismic adequacy reviews under the provisions of USI A-46, is included as Appendix A

to NUREG-1211.

Sincerely, Harol R. Denton, Director Office of Nuclear Reactor Regulation Enclosures:

1. NUREG 1211

2. NUREG 1030

cc: Service List Distribution:

Central File DSRO Chron File K

EIB Reading File 8703060307 H. Denton R. Vollmer A

F. Hebdon S. Rubin T. Speis B. Sheron R. Bosnak N. Anderson T. Y. Chang

(* see previous concurrence)

OFC :EIB:DSR0,*> EIB:DSRO :EIB:DSRO :DD:DSRO :D:DSRO :DDfiRR

NAMIE :*TChang/vt  :*NAnderson/ :*RBosnak  :*BSheron  :*TSpeis :R er DATE 3/6 /87 :3/ /87 :3/ /87 :3/ /87 :3/ /87 --- - 87 *

OFFICIAL RECORD COPY

The second LER concerned emergency diesel generator switchgear cabinets at the Cooper plant that were not fastened to embedded channels beneath the cabinets (LER 86-009). The third deficiency was found at the Dresden 2 and 3 plants, where It was determined that the control room control panels did not have positive anchorage to the floor (LER 86-009). In each instance, the deficiency had existed since plant construction and was the result of installation errors, since the design drawings had specified seismic anchorage. As a consequence of these events, a review was initiated by the NRC Office for Analysis and Evaluation of Operational Data (AEOD). This review included an LER search which revealed four other instances of inadequate seismic anchorage or support of safety related electrical equipment plus other related seismic inadequacies. This information is documented in AEOD report "Seismic Anchors for Electrical and Control Panels" (AEOD/E611).

We are enclosing the generic letter which was issued to each nuclear plant that is required to perform seismic adequacy reviews under the provisions of USI A-46, the regulatory analysis (NUREG 1211) and the USI A-46 Technical Findings (NUREG 1030) for your information.

Sincerely, Orifinal Signed 8hy richard H.Vollmer Harold R. Denton, Director Office of Nuclear Reactor Regulation Enclosures:

1. Generic Letter

2. NUREG 1211

3. NUREG 1030

cc: Service List Distribution:

Central Fi S. Rubin DSRO Chron File T. Speis EIB Reading File B. Sheron H. Denton R. Bosnak R. Vollmer N. Anderson F. Hebdon T. Y. Chang

(* see previous concurrence)

OFC :EIB:DSRO :EIB:DSRO :DD:DSRO :D:DSRO :DD:WRRI zD:

---

___:------------: ------------ :-  :----i:------ ------_____

NAME :NAnderson/dw* RBosnak* :BSheron* :TSpeis* :RYV r :HD~tit n :

_____ __ _________ ________ ___ _. -------- :-- -----------

DATE :2/ /87 :2/ /87 :2/ /87 :2/ /87 :2t /87 :2/2(/87 OFFICIAL RECORD COPY

y S - aS

- -I

VAC power were found to lack the required door bolts. The second LER concerned emergency diesel generator switchgear cabinets at the Cooper plant that were not fastened to embedded channels beneath the cabinets (LER 86-009). The third deficiency was found at the Dresden 2 and 3 plants, where it was determined that the control room control panels did not have positive anchorage to the floor (LER 86-009). In each instance, the deficiency had existed since plant construction and was the result of installation errors, since the design drawings had specified seismic anchorage. As a consequence of these events, a review was initiated by the NRC Office for Analysis and Evaluation of Operational Data (AEOD). This review included an LER search which revealed four other instances of inadequate seismic anchorage or support of safety related electrical equipment plus other related seismic inadequacies.

We are enclosing the generic letter which was issued to each nuclear plant that is required to perform seismic adequacy reviews under the provisions of USI A-46, the regulatory analysis (NUREG 1211) and the USI A-46 Technical Findings (NUREG 1030) for your information.

Harold R. Denton, Director Office of Nuclear Reactor Regulation Enclosures:

1. Generic Letter

2. NUREG 1211

3. NUREG 1030

cc: Service List Distribution:

Central File DSRO Chron File EIB Reading File H. Denton R. Vollmer F. Hebdon S. Rubin T. Speis B. Sheron R. Bosnak N. Anderson T. Y. Chang OFC :EIB:DSRO :EIB:DSi DD: :D: D :DD:NRR :D:NRR

- - - - ------ ----- -----------

NAME :NAnders / w RBosn -:B eron  : peis :RVollmer :HDenton

____ -------

_______ --- -- -- -- -- -- -- -- ------------ -----

DATE :2/#3 /87 :2//Ig7

& :2/L187 1 2/l 87 :2/ /87 :2/ /87 OFFICIAL RECORD COPY