ML20214R460
| ML20214R460 | |
| Person / Time | |
|---|---|
| Site: | Seabrook, 05000000 |
| Issue date: | 08/27/1986 |
| From: | Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Novak T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20213F044 | List: |
| References | |
| FOIA-87-271 NUDOCS 8706080150 | |
| Download: ML20214R460 (2) | |
Text
AUG 2 71986 i
Docket No. 50-443 MEMORANDUM FOR:
Thomas M. Novak, Acting Director, Division of PWR Licensing-A, NRR FROM:
William F. Kane, Director, Division of Reactor Projects, Region I
SUBJECT:
ATTACHMENT 1 TO M K STATION UNIT 1 OPERATING LICENSE As requested in your June 6,1986 memorandum, Region I is forwarding Attachment 1, " Work Items to be Completed," for incorporation into the Seabrook Station, Unit 1 Operating License, NFF-56.
The enclosed attachment identifies preoperational tests and other items which must be completed to the NRC's satisfaction and iden-tifies required timing for their completion.
It should be noted that certain fire protection construction activities have not been completed (e.g., fire doors, sealant, conduit wrap, cable tray cover instal-lation, fire damper testing).
The licensee has indicated their intention to sta-tion fire watches to compensate for these uncompleted activities. We understand NRR is considering removing fire protection requirements from the improved techni-cal specifications.
In light of thi's, Region I recommends that Section 2.C.4 of the draft license be evaluated to determine the completeness and enforceability of all fire protection requirements.
Ofl8 M sign e g William F. Kane, Director Division of Reactor Projects
Enclosure:
As Stated bec w/ enc 1:
A. Cerne T. Elsasser E. Wenzinger D. Haverkamp RI:D RI:
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ENCLOSURE ATTACHMENT 1 TO NPF-56 This attachment identifies preoperational tests and other items which must be com-pleted to NRC's satisfaction and identifies required timing for their completion.
1.
Adopt final approved procedures for Modes 2 through 5 one week prior to en-i tering the mode for which they are required.
2.
Prior to criticality:
Complete preoperational testing and test results review for the following
+
a.
modified systems and components:
(1) Emergency feedwater (ST-51, ST-53, ST-55).
(2) Steam dump and main steam isolation bypass valves (ST-55).
(3) Pressurizer power-operated relief valves (PT 40.1 test exception).
b.
Provide satisfactory engineering solutions to outstanding construction deficiencies (10 CFR 50.55(e) reports).
Reinspect for liner detachment problems in selected sections of the ser-c.
vice water system piping which were repaired as part of a reported con-struction deficiency corrective action.
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