ML20214R460: Difference between revisions

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#REDIRECT [[IA-87-271, Forwards List of Preoperational Tests & Other Items Which Must Be Completed to NRC Satisfaction,Per 860606 Request. Certain Fire Protection Const Activities Have Not Been Completed.Licensee Intends to Station Fire Watch]]
{{Adams
| number = ML20214R460
| issue date = 08/27/1986
| title = Forwards List of Preoperational Tests & Other Items Which Must Be Completed to NRC Satisfaction,Per 860606 Request. Certain Fire Protection Const Activities Have Not Been Completed.Licensee Intends to Station Fire Watch
| author name = Kane W
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
| addressee name = Novak T
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000000, 05000443
| license number =
| contact person =
| case reference number = FOIA-87-271
| document report number = NUDOCS 8706080150
| package number = ML20213F044
| document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE
| page count = 2
}}
 
=Text=
{{#Wiki_filter: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:  P        QI:              I' i  y                                    W l  Waverkamp/meo          El{s er      0 Wenz nger          d t
8/27/86                  (y;            g31 0FFICIAL RECORD COPY 8706080150 870602 l PDR    FOIA                                                                    j k
GRABER87-271        PDR
 
        >                                                                                                                        r p'
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:
+
: a. Complete preoperational testing and test results review for the following 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).                                                            <
: c. Reinspect for liner detachment problems in selected sections of the ser-vice water system piping which were repaired as part of a reported con-struction deficiency corrective action.
e e
I' i            -
2
                                                                                                                                    )
I i
                                                                                                                          .}}

Latest revision as of 03:21, 6 August 2021

Forwards List of Preoperational Tests & Other Items Which Must Be Completed to NRC Satisfaction,Per 860606 Request. Certain Fire Protection Const Activities Have Not Been Completed.Licensee Intends to Station Fire Watch
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: P QI: I' i y W l Waverkamp/meo El{s er 0 Wenz nger d t

8/27/86 (y; g31 0FFICIAL RECORD COPY 8706080150 870602 l PDR FOIA j k

GRABER87-271 PDR

> r p'

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:

+

a. Complete preoperational testing and test results review for the following 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). <
c. Reinspect for liner detachment problems in selected sections of the ser-vice water system piping which were repaired as part of a reported con-struction deficiency corrective action.

e e

I' i -

2

)

I i

.