ML20237J093
| ML20237J093 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/31/1987 |
| From: | Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Campbell G ARKANSAS POWER & LIGHT CO. |
| References | |
| IEB-85-003, IEB-85-3, NUDOCS 8709030491 | |
| Download: ML20237J093 (3) | |
Text
_ _ -
f eM f
I In Reply Refer To:
AE 3 I m
-Dockets: 50-313 Arkansas Power & Light' Company l
ATTN:
Mr.' Gen'e Campbell 1.
Vice President, Nuclear Operations P. O. Box 551 Little Rock, Arkansas 72203 I
Gentlemen:
Thank you 'for your letters of May 15, July 16, October 1, and December 26, 1986, and March.27, 1987, containing your responses to IEB 85-03,
" Motor-0perated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings." Our review of these responses indicates the need for additional information before the program to assure valve operability can be-approved.
The specific information necessary for.the completion of our review is enclosed.- You are requested to supply the additional information within 30 days of the date of this letter.
Should you have any questions concerning this request, we will be pleased to i
discuss -them with you.
Sincereig,;g;nal Signed by:
J. E. GAGLIARDO I
0709030491(($$$313 ADOCK pon gg J. E. Gagliardo, Chief P
Reactor Projects Branch l
cc w/ enclosure:
l J. M. Levine, Director Site Nuclear Operations Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 Arkansas Radiation Control Program Director bec to DMB (IEll) bec distrib. by RIV:
RPB RRI R. D. Martin, RA R. E. Ireland RPSB Section Chief (RPB/B)
D. Weiss, RM/ALF D. E. Norman i
RIV DRSP RSB MIS System RSTS Operator Project Inspector, RPB R. Hall G. Dick NRR Project Manager T. F. Westerman l
PI' C:RP C:RPB JEGagi k o A'j AI-87-313 ME y
DRHu r
08/2g /87 084T87 08/31/8V IhI
y l'
i
&ev c L JS a i -2.
t Page 1 of 2 i
REQUEST FOR ADDITIONAL INFORMATION (RAI) RE:
l
_ Review of Responses to Action Item e of IE Bulletin 85-03 l
1 i
I Licensee:
Unit (s): Arkansas 1 Arkansas Power & Light Company Date of Response: 05-14-86 l
P.-0. Box 551 07-16-86 i
Little Rock, Arkansas 72203 10-01-86 12-26-86 03-27-87 l
Respondent:
J. Ted Enos Manager, Nuclear Engineering and i
Licensing 1
The information provided in your response to Action Item e of IE Bulletin 85-03 was found to be deficient in some areas.
Please provide the additional information necessary to resolve the following comments and questions:
- 1. Unlisted MOVs CF-Vil and CF-V1B in discharge lines of the core flooding tank safety injection system are shown normally open on FSAR Figure 6-2, Amendment 3.
The possible problem that the i
system would be inoperable if_the MOVs were left closed inadvertently should be addressed.
Based on the assumption of inadvertent equipment operations as required by Action Item a of the bulletin, revise Table 1 of the response of May 14, 1986 to include these valves.
2.
Unlisted MOV CV-1234 is shown normally open in one of the high pressure injection lines to Reactor Coolant Loop A.
Refer to Zone D-6 of Drawing M-231, Sheet 1, Revision 39.
Similarly located MOVs in two comparable B&W facilities are listed to ensure examination for maximum differential pressure.
Please justify or correct the exclusion of MOV CV-1234 from Table 1 of the response of May 14,1986, giving particular consideration to the effect of inadvertent operation.
- 3. Has water hammer due to valve closure been con-idered in the determination of pressure differentials?
If not, please explain.
4 Please state the planned date of completion of Action Item f of the bulletin.
Note that the'due date specified b-the bulletin is January 15, 1988.
i
r%
E x e. a surrL E.
Page 2 of 2 RAI for Arkansas 1
- 5. Please expand the proposed program for action items b, e and d of the bulletin to include the following details as a minimum:
(a) commitment to a training program for setting switches, maintainin8 valve operators, using signature testing equipment and interpreting signatures, and (b) description of the calculational method for extrapolating valve stem thrust when it is determined by testing at less than maximum differential pressure.
l
__