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, 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, Crane
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-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" TO: 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 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 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, 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.

K-t I The information developed in resolving USI A-46 is described in the to this letter and is being provided to you for information only.enclosures 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 of CARtD 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 related electrical equipment plus other related seismic inadequacies.

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, 1 I A T.I -.I I .Enclosures:

L NUREG 1211;2. NUREG 1030 cc: Service List':i k Harold R. Denton, Di Office ul ear_2R RegulationI

.., I L II.i.,.I I.I

.r ._ _, A LIST OF RECENTLY ISSUED GENERIC LETTERS ' i " Generic Letter No.Date of I ssuance Subject Issued To GL 87-02 -: ', , I VERIFICATION

OF SEISMIC 02/19/87 ADEQUACY OF MECHANICAL

AND ELECTRICAL

EQUIPMENT

IN OPERATING

REACTORS CUSI A-46)ALL HOLDERS OF OPERATING LICENSES NOT REVIEWED TO CURRENT LICENSING CRITERIA ON SEISMIC QUALIFICATION

OF EQUIPMENT 4A 'GL 87-01 PUBLIC AVAILABILITY

OF THE NRC 01/08/87 OPERATOR LICENSING

EXAMINATION

QUESTION BANK ALL POWER REACTOR LICENSEES

AND APPLICANTS

FOR AN OPERATING LICENSE GL 86-17 AVAILABILITY

OF NUREG-11699"TECHNICAL

FINDINGS RELATED TO GENERIC ISSUE C-B BWR MSIC LEAKAGE AND LEAKAGE CONTROL SYSTEM 1017/m6 10/22/e6 ALL LICENSEES

-4-OF BOILING .WATER REACTORS : -,.I-'GL 86-16 GL 66-15 GL 86-14 GL 86-13 6L 86-12 WESTINGHOUSE

ECCS EVALUATION

MODELS INFORMATION

RELATING TO COMPLIANCE

WITH 10 CFR 50.49,"EQ OF ELECTRICAL

EQUIPMENT IMPORTANI

TO SAFETY" OPERATOR LICENSING EXAMINATIONS

POTENTIAL

INCONSISTENCY

BETWEEN PLANT SAFETY ANALYSES AND TECHNICAL

SPECIFICATIONS

CRITERIA FOR UNIQUE

PURPOSE

EXEMPTION

FROM CONVERSION

FROM THE USE OF HEU FUEL 08/20/86 07/23/86 07/03/e6 ALL PRESSURIZED

WATER REACTOR APPLICANTS

AND LICENSEES ALL LICENSEES.

AND HOLDERS OF AN APPLICATION

FOR AN OPERATING LICENSE *ALL POWER -- F REACTOR LICENSEES

AND-APPLICANTS

ALL POWER REACTOR LICENSEES

WITH CE AND B&W PRESSURIZED

WATER REACTORS ALL NON-POWER REACTOR 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* :RY V r :HD~tit n :_____ __ _________

________ ___ -------- :-- _-. -----------

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

S y -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