ML20235G892

Summary of 870828 Meeting W/Util Re Justification for Continued Operation W/High Containment Temps.List of Attendees & Table of Contents from 870828 Justification for Continued Operation Encl

ML20235G892
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/24/1987
From:	Dick G Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8709300278
Download: ML20235G892 (8)

Text

- - _ - _ _ _ _ _ _ - _ - _ - _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ -_

i e .o

[p ato 'c UNITED STATES

, l' , , c (',j NUCLEAR REGULATORY COMMISSION

- "/ g WASHINGTON, D. C. 20555 k [ September 24, 1987 Docket No. 50-313 LICENSEE: Arkansas Power and Light Company (AP&L)

FACILITY: Arkansas Nuclear One, Unit 1 (ANO-1)

SUMMARY

OF MEETING BETWEEN THE STAFF AND ARKANSAS POWER AND LIGHT (AP&L) REGARDING THE JUSTIFICATION FOR CONTINUED OPERATION (JCO) WITH HIGH CONTAINMENT TEMPERATURES, AUGUST 28, 1987.

BACKGROUND In early August 1987, it was determined that ANO-1 was operating with contain-ment temperatures ranging from 103 F to 183 F, with an average of about 140 F.

This compares with a normal average temperature of 110 assumed in the FSAR, and an equipment qualification temperature of 120 F. Following a r. umber of discussions between the staff and licensee (see Meeting Summary dated August 28, 1987), the staff requested the licensee to submit a JC0 on August 28, 1987.

Pending staff review of the JC0, a decision would be made concerning continued plant operation.

SUMMARY

An initial meeting was held between AP&L and NRC management to discuss the general approach and bases for the JCO. An attendance list is included in Enclosure 1. AP&L stated that they had made a review of the effect of high containment temperatures and concluded that the plant is safe to continue to operate until the scheduled mid-cycle outage. AP&L indicated that they had brought a number of technical and support personnel with them and were prepared to sit with the NRC staff to answer questions and provide any additional information that the staff needed. In response to NRC questions, AP&L stated that they believed that they had addressed all critical areas that might have been affected by the temperatures.

AP&L summarized the scope of the JC0 by reviewing with the NRC the JC0 Table of Contents (Enclosure 2). AP&L was asked about the accuracy of containment tempera-ture profile; they responded that there are RTD data which were supplemented by infra-red measurements taken during containment entry on August 26, 1987. The actual values were compared to the calculated ones and found to be slightly lower. l 1

In response to a question about a specific cable failure, AP&L stated that the l cable in question was in an area of localized high temperature (pressurizer j vent block valve). The damaged cable was replaced with an improved type. AP&L 1

was asked if there were plans to go into containment to look at specific items, for example penetrations. AP&L stated that the preventative maintenance program was a major element in the program to continually assess the condition of critical equipment items.

8709300278 870924 PDR ADOCK 05000313 P PDR

- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ ___ _____J

-2 AP&L stated that they had taken several steps to avoid being in,similar situa-tions in the future. They initiated a review of all discrepancies identified {

during the ANO-1 start-up and the disposition of each discrepancy. Further, j AP&L is requalifying 50.59 reviewers, assessing the effectiveness of the j Safety Review Committee, and assigning additional technical people to the i plant.

l 1

The NRC stated that in addition to the effects of the harsh environment on com-ponents and structures, the higher temperatures made it difficult for personnel to enter containment. AP&L was told that the NRC wants to see the root cause fixed. AP&L indicated that an evaluation was underway to determine what long term actions should be taken. The evaluation is to be com pleted by January )

1988 after which a course of action will be set. At this point however, it  !

appears that there are three major factors that affect containment temperature. l They are chiller capacity, insulation, and air circulation within the building. {

At the end of the meeting AP&L was informed that the NRC would perform a l preliminary review of the JC0 during the afternoon. Following the technical review, the staff would caucus, reach a conclusion, and the conclusions and/or 1 com ments would be conveyed to AP&L management.

Following completion of the management meeting, the technical staff received copies of the JCO. It was reviewed by the following branches; Mechanical Engineering, Structural and Geosciences, Instrumentation and Control Systems, i Electrical Systems, Plant Systems, and Reactor Systems. In addition to review-l ing the JC0, the staff met with AP&L staff and their consultants. At the l j

conclusion of the meetings and reviews with AP&L, the staff reconvened. The i staff concluded that the JC0 was acceptable. It was agreed that the staff l would issue a Safety Evaluation documenting its conclusions and any licensee j commitments for actions or confirmatory information. J After the NRC meeting, AP&L management was informed by telephone of the staff's decisions.

l5l George F. Dick, Jr., Project Manager Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects

Enclosures:

As stated l cc w/ enclosures:

See next page Docket File NRC PDR Local PDR PD4 Reading T. Murley/J. Sniezek F. Miraglia F. Schroeder D. Crutchfield P. Noonan G. Dick OGC-Beth W. Lanning E. Jordan J. Partlow Receptionist (Phillips) l NRC Participants ACRS (10) GPA/PA l V. Wilson B. Kolostyak l LTR NAME: ' MEETING SUMMAR AN01 9/9 i APM PD4/D I y- '

PD4/LATk.

PNoon' a6 -

k:al JCalvo 96t/87 9/J4/87 9/af/87 L__________________

x -

'Mr. G. Campbell T Arkansas Power & Light Company Arkansas Nuclear One, Unit 1 Cc:

Mr. J. Ted Enos, Manager Nuclear Engineering and. Licensing

' Arkansas Power & Light Company P. O., Box 551 Little Rock, Arkansas 72203 Mr. James M. Levine, Director.

Site Nuclear Operations-Arkansas Nuclear One P. O. Box-608 Russellville, Arkansas ~72801 Mr. Nicholas.S. Reynolds Bishop, Liberman, Cook, Purcell & Reynolds 1200 Seventeenth Street,'.N.W.

Washington, D.C. 20036 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident Inspector

'U.S. Nuclear Regulatory Commission P. O. Box 2090 Russellville, Arkansas 72801 Regional' Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations i 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Mr. Frank Wilson, Director Division of Environmental Health Protection Department of Health Arkansas Department of Health 4815 West Markham Street Little Rock, Arkansas 72201 Honorable William Abernathy County Judge of Pope County '

Pope County Courthouse

-Russellville, Arkansas 72801 1

7 Enclosure 1 NRC/AP&L MANAGEMENT MEETING ATTENDANCE AUGUST 28, 1987 NRC AP&L J. Sniezek T.G. Campbell F. Miraglia J. Levine R. Starostecki J.T. Enos L. Shao R. Lane I l

F-. Schroeder J. Calvo G. Dick l l

Tenera H. Levin Middle South Utilities /SSI l W. Cottle l

1 i

l I

i l

l l

1 l

L l

i l

ENCLOSURE 2

't ELEVATED REACTOR BUILDING TEMPERATURE ARKANSAS NUCLEAR ONE - UNIT i l

JUSTIFICATION '

FOR CONTINUED OPERATION i i

l' AUGUST 28, 1987 l ARKANSAS POWER S LIGHT COMPANY

)

33

• i .

. TABLE OF CONTENTS 4

Section Title Page i f'

EXECUTIVE

SUMMARY

I. ANO REACTOR BUILDING AIR TEMPERATURE HISTORY ....... 1-1

]

I.A REACTOR' BUILDING AIR TEMPERATURE HISTORY ............. 1-1 1

1.B EQUIPMENT PROBLEMS RELATED T0 REACTOR BUILDING )

ELEVATED AIR TEMPERATURE ............................. 1-2 )

I.C. BASES FOR SAR REACTOR BUILDING AIR TEMPERATURE VALUE ................................................ I-3 1.0 REACTOR BUILDING STRUCTURAL DESIGN ................... I-6 1.E PLANT OPERATING HISTORY .............................. I-6 I.F INVESTIGATION OF CURRENT REACTOR BUILDING TEMPERATURES ......................................... I-7 II. SAFETY ANALYSESE..................................... 11-1 II.A REANALYSIS OF ANO-1 TO CONSIDER ELEVATED REACTOR BUILDING TEMPERATURES ........................ 11-1 II.A.1 Safety Analysis Report, Operating License and Associated Technical Specifications, and Safety Evaluation Report Review ..... ... ............ 11-1 II.A.2 Regulatory Correspondence Review ..................... 11-8 II.A.3 Additional Reactor Building Pressure /

Temperature Response Analyses ........................ II-11 II.A.4 Chapter 14 Analyses .................................. 11-14 II.B REACTOR BUILDING STRUCTURAL INTEGRITY II.B.1 Introduction II.B.2 Internal structure Impacts II.B.3 Equipment Support and Anchorages II.B.4 Piping Systems II.B.5 Cranes and Fuel Handling Equipment Inside Containment  !

II.B.6 Auxiliary Systems

f t-- .

TABLE OF CONTENTS Section Titig Pa2' II.B.7- Sump Debris

, II.C ENVIRONMENTAL QUALIFICATION 11.0 EVALUATION OF NON-EQ EQUIPMf.HT INSIDE THE REACTOR BUILDING II.D 1 Mechanical Equioment 11.0.2 Electrical Equipment II.D.3 Instrumentation and Controls II.D.4 Maintenance Program II.D.5 Conclusion II.E. EVALUATION OF~ ELEVATED TEMPERATURE EFFECTS ON EQUIPMENT AND SYSTEMS OUTSIDE REACTOR BUILDING II.E.1 Methodology II.E.2 General Design Requirements II.E.3 System Overview II.E.4 Survey Results II.E.5 Heat Gain Evaluation II.E.6 Conclusions III. EVALUATION OF POTENTIAL IMPACTS ON ANO-2

~

III.A DESIGN CONDITIONS .................................... III-1 III.B SAFETY ANALYSES AND TECHNICAL SPECIFICATIONS . . . . . . . . . III-2 III.C PERFORMANCE OF THE ANO-2 CONTAINMENT ................. III-2 l 1

1

11.0 CONCLUSION

........................................... III-4 IV. ACTIONS IV.A ANO-1 ................................................ IV-1 IV.A.1 Immediate Actions ....................... .............. IV-1 IV.A.2 N e a r Te rm A c t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-3

i t .

TABLE OF CONTENTS I

P_ age  !

Section Title Long Term Actions .................................... IV-7 IV.A.3 1

IV-9 j Iv.B ANO-2 ................................................

i l

SUWARY AND CONC LUSIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-1  !

V. <

{

l ._______ - _ -