ML18017B328

Interim Deficiency Rept Re Heating,Ventilation & Air Conditioning for Class IE Motor Control Ctrs,Initially Reported on 801017.Design Change Has Been Developed.Final Rept Will Be Issued by 811231

ML18017B328
Person / Time
Site:	Harris
Issue date:	02/16/1981
From:	Chiangi N CAROLINA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8102250081
Download: ML18017B328 (7)

Text

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ACCESSION NOR: 6102250061 DOC, DATE: S1/02/16 NOTARLZED: NO DOCKET ¹ I-AGIL:bo 400 Shearon Harris Nuclear Power Plant~ Unit l~ Carolina 05600400

'-'o-HI bhearon Harris Nuclear Power Plant~ Unit 2~ Carolina oSootI4oi So" 4tl2 Shea'ron Harris Nuclear Power Ptantq Unit 3~ Carolina OSOOO4O2 50 H3 8hearon Harris Nuclear power I lant< Unit ~1i Caro'lina osooo4o3 au'r H, IIAMt. auTHux at.FT'LraTioN GIiXaAt,"I'",N,J. Carolina Vower tc Light Co ~

REL1'P NaMi AECII'IEN I AFFILIATION O'AEICLYiJ ~ P ~ Region 2i Atlanta; Uf fice of the Director SUBJEC'l': Interim deficienc y rept re heating~ventilation L air I condi.tfoning for t:lass IE 'motor control ctrsiinitiat ly r epoi ted on 60101 7'esign change has been developed.Final rept wi l be issu ed by 811231.

1 DISTRIBUTION CODE: 8 019S COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Construction Defici ency Repor t (10CFA50.55E)

NOTES:

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FGRM 21 Carolina Power 8 Ught Company Ratefgh, N.C. 27602 Pile: SH N/2-18 Item 52 Pebruary 16, 1981 Mr.'ames P. O'Reilly United States Nuclear Regulatory Commission Region II 101 Marietta Street, Northwest Atlanta,, Georgia 30303 SHEARON HARRIS NUCLEAR POWER PLANT UNITS 1, 2, 3 AND 4 DOCKET NOS. 50-400, 50-401, 50-402 AND 50-403 NONSAPETY HVAC POR CLASS 1E MOTOR CONTROL CENTERS - INTERIM REPORT

Dear Mr. O'Reilly:

~

our November 24, 1980, interim report on the subject deficiency, we had

'er indicated that all corrective action would be completed by Pebruary 15, 1981, at which time the final 10CPR50.55(e) report would be submitted. The intent of this letter is to inform you that due to the extensive nature of the scope of the subject problem, all corrective action has not yet been completed.

Attached is an interim report which provides an update of the problem investi-gation/resolution. It is now anticipated that all corrective action excluding equipment qualification or relocation to environmentally controlled areas will be completed by May 1, 1981, and that the equipment qualification or relocation to environmentally controlled areas will be completed by December 31, 1981, at which time the final 10CPR50.55(e) report will be submitted.

Thank you for your consideration in this matter.

NJC/mt (3807)

Attachment Oi'ipl3ll Elgr78d l3y cc: Mr. G. Maxwell W/A N. J. Chiangi Mr. V. Stello (2) W/A~

N. J. Chiangi - Manager gP 8

CD Engineering 6 Construction Quality Assurance CD'l CD "Cr.~

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SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 NONSAFETY HVAC FOR CLASS 1E MOTOR CONTROL CENTERS Interim Report No. 2 February 13, 1981 Reportable Under 10CFR50.55(e)

Prepared by: Carolina Power & Light Company

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SUBJECT:

10CFR50.55(e) Reportable Item Shearon Harris Nuclear Power Plant (SHNPP)

Nonsafety HVAC for Class lE Motor Control Centers ITEMS:

MCC's lA-35SA, MCC 1B-35SB, 2A-35SA & 2B-35SB SUPPLIED BY: Design Ebasco Services, Inc.

NATURE OF DEFICIENCY:

Class lE Motor Control Centers are not cooled by safety-related HVAC, as stated in the SHNPP FSAR.

DATE PROBLEM WAS CONFIRMED TO EXIST: October 17, 1980 PROBLEM REPORTED:

October 17, 1980 CP&L (L. I. Loflin, K. V. Hate & R. K.

Cothren) informed the NRC Region II office (Mr. J. -K. Rausch) by telephone that t'.he problem was "potentially reportable" under 10CFR50.55(e).

October 27, 1980 - CP&L (N. J. Chiangi) informed the NRC Region II office (Mr. J; K. Rausch) by telephone that the problem was reportable under 10CFR50.55(e).

SCOPE OF PROBLEM:

Equipment located in the common area of the Reactor Auxiliary Building (RAB) between Units 1 & 2 at Elevations 261 and 236 are not supplied with safety-related HVAC and may not be qualified for the room temperatures which will bereached in the event that electrical power and hence, ventilation, is lost ~

REASONS (S) PROBLEM WAS REPORTABLE:

Class 1E equipment in the Unit One & Common Reactor Auxiliary Building is cooled by safety-related HVAC equipment in order to reduce the temperature extremes to which this equipment would be subjected in the event of a LOCA. The Motor Control Centers at the 261 elevation of the Units 1 & 2 Common RAB 0 are Class 1E and are qualified to a room temperature of 104 F .

(40 C). The normal HVAC for this elevation, as well as the 236'ommon RAB elevation, has a Non-1E power supply. In the event of a loss of HVAC, the temperature in the area of the Motor 0

Control Centers could exceed 104 F (piping containing 120 F fluid passes through this area). Since the Motor Control Centers are not qualified .for temperatures above 104 F, the continued functioning of the MCCs cannot be certified.

This condition deviates from the SHNPP FSAR Section 3.11.4.1 which states that "Plant areas containing ESF and RPS equipment and their ~su ort ~s stems are temperature oontrolled to provide a controlled environment even during the most severe DBA condition."

Since the design of the Unit 1 and Common RAB has been approved and released for construction, this condition constitutes a significant deficiency which does not conform to the criteria and bases stated in the Safety Analysis Report.

CORRECTIVE ACTION:

A design change has been developed and issued for incorporation which adds safety-related HVAC units at the 286 elevation of the Unit 1 and Common Reactor Auxiliary Building. These HVAC units will provide safety-related ventilation to MCCs 1A-35SA, 1B-35SB, 2A-35SA, and 2B-35SB.

In addition, the architect-engineer (Ebasco) prepared detailed temperature maps. of the plant in order to verify that no such condition existed 'elsewhere in the plant. A detailed review of each equipment item against the temperature expected to exist in the area of the plant where the item is logated has ~

been completed, resulting in the identification of some ESF-related (Class lE) instrumentation which is presently not located in'nvironmentally-controlled areas. This equipment will be qualified to the maximum post-accident tempeiatures, determined for each location or will be relocated to environmentally-controlled areas.

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