ML20236F773
| ML20236F773 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/29/1987 |
| From: | Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Campbell G ARKANSAS POWER & LIGHT CO. |
| References | |
| IEIN-85-003, IEIN-85-3, NUDOCS 8708040026 | |
| Download: ML20236F773 (2) | |
Text
..
Iti Reply Refer To:
M_ g g ggy Dockets:
50-368 Arkansas Power & Light Company ATTN: Mr. Gene Campbell Vice President, Nuclear Operations P. O. Box 551 Little Rock, Arkansas 72203 Gentlemen:
Thank you for your letters of May 14, 1986, and October 1, 1986, in response to IE Bulletin 85-03, dated November 15, 1985.
As a result of our review, we find that additional information is needed.
Specifically, the information provided in your response to Action Item e was found to be deficient in some areas.
Please provide the additional information necessary to resolve the following comments and questions.
1.
Unlisted MOVs 5003-1, 5023-1, 5043-2, and 5063-2 in discharge lines of the safety injection tank system are shown locked open on Drawing M-2232, Revision 50.
If power is removed from the motors in addition to the locked-npen position of these MOVs, please state this in your response.
Otherwise, address the effect of assuming inadvertent equipment operations as required by Action Item a of the Bulletin, and revise Table 1 of the response of May 14, 1986, to include these valves.
2.
Hn water hammer due to valve closure been considered in the determination of pressure differentials?
If not, please explain.
3.
Listed MOVs 5101-1 and 5102-2 of the HPSI System are 3-inch globe valves, and listed MOVs 1025-1 and 1075-1 of the EFW System are 4-inch globe valves. We were advised recently that the M0 VATS data base does not include globe valves with orifice sizes less than 1.75 or greater than 2.0 inches. Will representative samples of these 3-inch and 4-inch globe-valves be tested at full differential pressure?
If not',' explain and justify how settings will be verified for full differential pressure.
Although valve signature testing is not mentioned in the response identified above, it should be noted that it was stated in NRC Inspection Report 86-32, dated December 24, 1986, that "the licensee has implemented a program to ensure reliable operation of MOVs utilizing the Motor Operated Valve Analysis and Test System (M0 VATS)..."
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4.
Please expand the proposed program for action items b, c, and d of the 4
Bulletin to include the following details as a minimum:
i (a) description of the training program for setting switches,.
maintaining valve operators, using signature testing equipment j
and interpreting signatures, and 1
(b) description of the method (s) to be used to extrapolate valve stem j
thrust measured at less than maximum differential pressure.
j l
5.
Please submit a date for planned completion of Action Item f of the l
Bulletin.
The specified due date is January 15, 1988.
l i
Please provide the supplemental information within 30 days of the date of the letter.
Sincerely, Orinnal Si ned by:
t J. E. G AGLIARD.]
)
J. E. Gagliardo, Chief Reactor Projects Branch
]
cc J. M. Levine, Director Site Nuclear Operations Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 i
Arkansas Radiation Control Program Director bec to DMB (IE11) l I
l bec distrib. by RIV:
1
- RPB
- RRI R. D. Martin, RA RPSB
- Section Chief (RPB/B)
- RIV DRSP
- RSB P. Kiessel, NRR
- Project Inspector, RPB
- R. Hall
- G. Dick, NRR Project Manager Section Chief (RSB/ES) t D. Norman AI 87-239 u