ML20094A958
| ML20094A958 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf |
| Issue date: | 07/30/1984 |
| From: | Dale L MISSISSIPPI POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| ACEM-84-0402, ACEM-84-402, TAC-56575, NUDOCS 8408060174 | |
| Download: ML20094A958 (7) | |
Text
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l MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi M
P. O. B O X 164 0, J AC K S O N, MIS SIS SIP PI 3 9 2 05 July 30,1984 NUCLE AR LICENSING & SAFETY DEPARTMENT Mr. Darryl G. Eisenhut U.S. Nuclear Regulatory Commission 1717 H Street, N.W.
Washington, D.C. 20036
Dear Mr. Eisenhut:
SUBJECT:
Grand Gulf Nuclear Station Units I and 2 Docket Nos. 50-4I6 & 50-417 License No. NPF-13 File: 0260/L-860.0 SRV Solenoid Valves AECM-84/0402 In response to the requirements of NUREG-0588 concerning environmental qualification of the Safety Relief Valves and their associated solenoid valves, MP&L submitted results of testing which justified interim operation pending full qualification as required by 10 CFR 50.49. Those results were transmitted by letter AECM-81/355.
A successful Design Basis Accident (DBA) test of four day duration was performed after thermal, mechanical and radiation aging. Attachment I contains details of the specifications and environmental profiles. MP&L considered this a i
successful test, but due to a limited qualified life and somewhat short DBA test time, it was determined that further enhanced testing would be undertaken.
Retesting of the SRV solenoid volves in accordance with IEEE-323-74 was initiated in September of 1982. The valves were functionally checked after each phase of testing and proved they could perform the required functions at on end of service life condition through 486 hours0.00563 days <br />0.135 hours <br />8.035714e-4 weeks <br />1.84923e-4 months <br /> of a Main Stream Line Break / Loss of Coolant Accident. At this point the valve failed to operate and was removed from the chamber for an evaluation.
7 Prior to failure, the valve had been irradiated to 6.65 x 10 Rads from a Cobalt-60 source, thermally aged for 823.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> at 1500C, operationally cycled I100 times, sei.mically tested and installed in on environmental chamber and exposed to a LOCA profile for 486 hours0.00563 days <br />0.135 hours <br />8.035714e-4 weeks <br />1.84923e-4 months <br />.
Therefore, the SRV associated solenoid valves have been shown to function under Grand Gulf environmental test conditions for in excess of 20 days. Recently, while under environmental testing for the Nine Mile Point Project 2, failure of an SRV associated solenoid was noted.
As stated, this failure was for a qualification test for the General Electric Mark ll containment. The required test parameters were significantly in excess of those required for the Grand Gulf Mark lli containment.
8408060174 840730
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PDR ADOCK 05000416 f
P PDR Member Middle South Utilities System l
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I AECM-84/0402 MISSISSIPPI POWER CI LICHT COMPANY 9#
h 1 provides a detailed comparison of the General Electric, Nine Mile Point qualification requirements versus those required for Grand Gulf.
As con be seen, the recent General Electric test far exceeds that required for Grand Gulf. Due to the failure mode of seal failure, the two parameters of most interest are the very high radiation exposure and containment pressure, in summary, MPAL believes that the environmental integrity of Grand Gulf SRV's and their a:sociated solenoid valves are adequate for interim operation pending full qualification testing because, I)
The Grand Gulf SRV's successfully passed a DBA qualification test as documented in AECM-81/355 (see Attachment I).
2)
Further testing has shown successful operation for in excess of 20 days, under the required Grand Gulf accident profile.
Additionally, MP&L believes that the recent SRV solenoid failure experienced by General Electric is not applicable to Grand Gulf because the accident environment for the General Electric test was based on a Mark 11 containment environment which is for more severe than the environment for the Grand Gulf Mark 111 containment.
Sincerely, L$
f[,., L. F. Dale Manager, Nuclear Licensing & Safety LFD/ sod cc:
Mr. J. B. Richard Mr. R. B. McGehee Mr. N. S. Reynolds Mr. G. B. Taylor Mr. Richard C. DeYoung Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. J. P. O'Reilly Regional Administrator U.S. Nuclear Regulatory Commission Region ll 101 Marietta Street, N.W., Suite 2900 Atlanta, GA 30323
r AtBOchsont 8 NUCLEAR PLANT ENGINEERING NURZG 3::88/leCFR50.49 ECUIPMENT GENERIC NAME:
MSSRV MANUFACTURER: Dikkers-Seita ROOM NUMBER 1A112 QUALIFICATION STATUS : 10J EQ CENTRAL FILE BOOM #s G34 QUALIFIED LIFE e48 YRS SPEC / PPD #
81921-F051 PART DESCRIPTION: MIAN STEAM SRV ACTUATOR PLANT ID #
s1921-Fast A MODEL #
- SEE EQ FILE BK.
TEST REPORT # TAO-313-GH REV1 l'~~PINIUEYER SPECIFiCIii6U~E5VIRONMENT I
l
____________i______.--
QUALIFICATION ENVIRONMEAT~
l
=___
________l____
IOPERATING TIME I 2 DYS ACT. 96 DYS PS I
4 DAYS ACTIVE ITEMPERATURE I 338F FOR 3 HOURS I
I 44.7 PSIA FCR 40 SEC 349F MAX FOR 3 HOURE IPRESSURE 1
(REL. HUMIDITY I ALL STEAM FOR 1 HOUR 52 PSIG FOR 1 HOUR IFLOODING/ FROTH I N/A ALL STEAM 9 NOURS 6
IRADIATION I
N/A I 21.1E6-G,1.SE9-BETA I
30.OE6 GAMMR lAGING I 5 YEARS,159 CYCLES 1
49 YEARS,1998 CY, flAD ICONTAINMENT SPRAY 1(((((((((((((((((l N/A I
N/A
(((((((((((
COMMENTS a IQJ PROVIDED IN AECM-41/355mereen numoer 1 ))))))))))))))))))))
I-i t
r-Attactanent E Sheet 1 of 4 C.E./GG5 PARAMEITR Cr29ARISQt G.E. TEST miHB PANW!ER RFOJ3tN N:15 REUERDefts 6
6 il Radiatiers Aging 300 x 10 Casma neds 44 x 10 Germa Reds (5 yr. anzvice life)
(40 yr. service life) 2)
'Ihormal Aging 300'F for 590 Hrs'.
300'T for 923.5 Ers.
(5 yr, service lite)
(40 yr. service life) 3)
Mechanical Aging 1237 cycles 200 cycles (5 yr. service life)
(5 yr. servloe life) 4)
DBA See Sheets 2 thru 4 See Sheets 2 thru 4 or this attachnent of this attactrant
m ATTACMMENT*.3Z' EWEET 2 OJr4 sss*v ar rua s s
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MlSERS$1PPI POWER & LIGHT COMPANY I
GRAND GULF NUCLEAR STATION UNIT 1 RESPONEE TO NUREG- 0688 ENVELOPING TEMPERATURE PROFILE
' FOR ROOMS: 1A112.1A113 (EXCEPT AS SHOWN ON FIGURE S 11),
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