ML19225A830
| ML19225A830 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/12/1979 |
| From: | Counsil W NORTHEAST UTILITIES |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| TASK-03-12, TASK-RR NUDOCS 7907200349 | |
| Download: ML19225A830 (3) | |
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N0lrI'HEA!iT UTil.lTIE!i z
P O BOX 270 l
HARTFORD. CONNECTICUT 06101
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July 12,1979 Docket No. 50-245 Director of Nuclear Reactor Regulation Attn:
Mr. D. L. Ziemann, Chief Operating Reactors Branch #2 U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Reference:
(1)
W. G. Counsil letter to D. L. Ziemann dated March 5,1979.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 1 Systematic Evaluation Program (FZP)
Electrical Equipment Environmental Qualification (EEQ)
In Refere.act (1), Northeast Nuclear Energy Company (NNECO) reviewed the electrical EEQ informt.t.on which had been compiled by the NRC Staff. As part of our con-tinuing ef for ts to update this information as our efforts progress, we are hereby submitting the attached additional documentation.
The attached pages have been modified from our letter of
- r. arch 5,1979 (Reference (1)) in order to include the limit switches on the main steam isolation valves.
Very truly ycurs, NORTHEAST NUCLEAR ENERGY CCMRANY 0,/,/)
l l
/Y,
-(Y{'7?0L l W. G. Counsil Vice President Attachment 2:
445 290 7907200343
MILLSTONE UNIT NO. 1 DOCUMENTATION REFERENCES (1) GE Test Report PEP-42963.
(2) August 8,1978 letter, Atkomatic.
(3)
Preliminary NUSCO Engineering Evaluation.
(4 ) Crane Test Report 7828-1, dated October 20, 1969.
(5) GE Test Report EPAQ-007, dated August 7, 1967.
(6) GE Test Report EPAQ-008, dated December 29, 1967 (7) GE Test Report EPAQ-009, dated Dec ember 12, 1967.
(8) GE Tcst Report EPAQ-010, dated December 12, 1967.
(9) FIRL Test Report F-C2770.
(10) FIRL Test Report F-C 3 8 5 9-1.
(11) FIRL Test Report F-C4C33-3.
(12) GE letter G-EH-8-37 dated March 31, 1978.
(13) Automatic Switch Company Catalog No. 30 issued September, 1977.
(14 )
Section VI Part 2.7.ld FSAR.
(15)
NUSCO Memo NEE-79-E-ll5, dated February 14, 1979.
(16) GE Test Report EPAQ-04 6.
(17) GE Test Report EPAQ-056, dated May, 1967.
(18 ) GE Test Report EPAQ-060, dated April 30, 1971.
(19) GE Test Report EPAQ-061, dated October 31, 1971.
(20)
Figure VI-2.25 FSAR.
(21) Figure VI-2.26 FSAR.
(22) Table 3.7.1 Technical Specifications.
(23) CE Test Report VPF #2793-543.
(24) GE Document 21A9206, Rev. 6.
(25) GE Plant Equipment Design Memorandum 126-62.
(26)
E&iSCO Purchase Order NY-481248.
(27) FIRL Test Report F-C3271.
(28) FIRL Test Report F-C 3441.
(29) FIRL Test Report F-C2232-01.
(30) Crane Letter of February 1, 1978.
(31) NAMCO Co n t rol s
'" s t Report.
(32)
Sec cion 4.1.1 of E Nuclear Energy Division Document 21A9206 (Rev. 6) datel Ianuary 21, 1974.
A circled reference number indicates that the reference is available and has been checked for applicabilley.
445 29i
. REACTOR: Millstone Unit No. 1 Svstematic Evaluation Program (Co n t inued )
SEP Submittal Time Environment Qual.
I Equipment Type Reference Loc Needed Parameter Spec.
Qual.
Method Reference 9.
11, 15 Splices 2-2/ 5 1
800 Temp.
291*F 357'E Test Raychem/
Pr. (Psia) 58 85 Tect Type WCSF-N RH 100%
100%
Test Chem.
.e 8
Rad.
i r 107 2 x 10 Test dub.
No 10.
31, 32 Limit Switches I
Temp.
150*F 34 0*F Test NAMCO Controls /
Pr. (Psia) 17 78 Test l
EA-740 RH 100%
100%
Test l
Chem.
No 7
8 Rad.
2.6 x 10 2 x 10 Test Sub.
No I
i 4%
_m U1 N
'O N