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=Text=
=Text=
{{#Wiki_filter:.  .        _.      .                        .          . . - _ _ _-_                                  .
{{#Wiki_filter:.
t '
t '
v: y                                                                                                                                   -
v: y New Hompshire?
                                                                                                                                              ;
o m.,
o      . New Hompshire?                                                                       m .,
Senior Vice President and '
Senior Vice President and '
Chief Operating Officer l                                                                             NYN-90010                                                     )
Chief Operating Officer l
January 11, 1990
NYN-90010
                                                                                                                                              ;
)
United States Nuclear Regulatory Commission Washingtoni DC- 20555 a
January 11, 1990 United States Nuclear Regulatory Commission Washingtoni DC-20555 a
Attention: Document Control Desk                                                                                               ,
Attention: Document Control Desk i
i


==References:==
==References:==
(a). Facility Operating License NPF-67,. Docket No. 50-443'                                                   l L
(a). Facility Operating License NPF-67,. Docket No. 50-443' l
(b) NRC Bulletin 88-09 . dated' July 26, 1988, " Thimble Tube.                                               I l
(b) NRC Bulletin 88-09. dated' July 26, 1988, " Thimble Tube.
Thinning-in Westinghouse Reactors' i
I L
Subject     Information Regarding Incore Instrumentation Thimble Thinning'                                                     ,
l Thinning-in Westinghouse Reactors' i
L            Gentlemen:                                                                                                                     i
Subject Information Regarding Incore Instrumentation Thimble Thinning' L
!                      This letter provides currently-available information regarding.the                                     .
Gentlemen:
                                                                                                                                            ;
i This letter provides currently-available information regarding.the
(            subject of incore instrumentation ' thimble thinning as it' applies to Seabrook l
(
Station. New Hampshire Yankee.(NHY) is planning to-provide the requested                                                     i i
subject of incore instrumentation ' thimble thinning as it' applies to Seabrook l
response to NRC Bulletin 88-09 following completion of the first). refueling outage of Seabrook Station Unit 1 in accordance with.the schedule specified                                                   i by the Bulletin.
Station.
The Seabrook Station fixed / movable incore instrumentation system features a                                                   ,
New Hampshire Yankee.(NHY) is planning to-provide the requested i
unique mechanical design which provides in-depth protection,against. reactor
response to NRC Bulletin 88-09 following completion of the first). refueling i
!            coolant leakage consequent to thimble wear. The'in-core instrumentation l           thimble contains fis:ed detectors. Consequently, the design Includes two concentric thimbles. The inner thimble permits the moveable = detector'to l           traverse the core and serves as the reactor: coolant pressure-boundary.- The l           outer thimble serves as the housing for the fixed incore'detectoru and                                                     --
outage of Seabrook Station Unit 1 in accordance with.the schedule specified i
:          incore thermocouples, which are located between the inner and outer                             ~
by the Bulletin.
thimbles. Failure of the outer thimble would not breach the reactor coolant-pressure boundary. Failure of both outer and inner thimbles would'be                                                             s
The Seabrook Station fixed / movable incore instrumentation system features a unique mechanical design which provides in-depth protection,against. reactor coolant leakage consequent to thimble wear. The'in-core instrumentation l
;.          required to breach-the reactor coolant pressure' boundary. -In the.h_ighly unlikely event of a wear-induced failure of both inner and outer thimbles,                                                       ;
thimble contains fis:ed detectors. Consequently, the design Includes two concentric thimbles.
isolation valves at the seal table can be used to terminate reactor = coolant                                                     '
The inner thimble permits the moveable = detector'to l
leakage.
traverse the core and serves as the reactor: coolant pressure-boundary.- The l
New Hampshire Yankee expects to develop .n inspection program to monitor thimble performance. The program will 'e based, in part, upon industry experience and' vendor recommendations. The program will'be-implemented at'
outer thimble serves as the housing for the fixed incore'detectoru and incore thermocouples, which are located between the inner and outer
                                                                                                                                      ..I
~
..          the first refueling outage of Seabrook Station Unit 1. The report 6                                                                                     .
thimbles.
confirming that the program has been established and that the initial                                                             .
Failure of the outer thimble would not breach the reactor coolant-pressure boundary.
thimble inspections have been performed in accordance with the requirements                                                     '
Failure of both outer and inner thimbles would'be required to breach-the reactor coolant pressure' boundary. -In the.h_ighly s
;
unlikely event of a wear-induced failure of both inner and outer thimbles, isolation valves at the seal table can be used to terminate reactor = coolant leakage.
of the program will be submitted within thirty (30) days of completion of
New Hampshire Yankee expects to develop.n inspection program to monitor thimble performance.
.          the inspections.
The program will 'e based, in part, upon industry experience and' vendor recommendations.
9001230028 900111 F                                                                 [
The program will'be-implemented at'
PDR   ADOCK 05000443                                                                             /
..I the first refueling outage of Seabrook Station Unit 1.
Q                     PDC                                                                     ,
The report 6
New Hampshire Yonkee Division of Public Service Company of New Hampshire                         (p               i P.O. Box 300
confirming that the program has been established and that the initial thimble inspections have been performed in accordance with the requirements of the program will be submitted within thirty (30) days of completion of the inspections.
[
9001230028 900111 F
PDR ADOCK 05000443
/
Q PDC New Hampshire Yonkee Division of Public Service Company of New Hampshire (p
i P.O. Box 300
* Seabrook, NH 03874
* Seabrook, NH 03874
* Telephone (603) 474 9521 -
* Telephone (603) 474 9521 -


    * .- I, United States. Nuclear Regulatory Commission       January 11, 1990-Attention: Document Control Desk                   Page 2.
I, United States. Nuclear Regulatory Commission January 11, 1990-Attention: Document Control Desk Page 2.
L             If you have any questions on this matter please contact Mr. Geoffrey
L If you have any questions on this matter please contact Mr. Geoffrey
[             Kingston at (603) 474-9521..
[
Very truly yours, h&f 4             &
Kingston at (603) 474-9521..
L                                                                Ted C. Feigenbaum     j cc:     Mr. William T. Russell
Very truly yours, h&f 4 L
: l.                   Regional Administrator l                     United States Nuclear Regulatory Commission                         ,
Ted C. Feigenbaum j
Region I                                                             '
cc:
l                    475 Allendale Road l                     King of Prussia, PA 19406                                         .;
Mr. William T. Russell l.
Mr. Victor Herses, Project Manager                                   !
Regional Administrator l
l                    Project Directorate I-3                                           j l                     United States Nuclear Regulatory Commission                         l l
United States Nuclear Regulatory Commission Region I l
Division of Reactor Projects                                         ;
475 Allendale Road l
i                     Washington, DC 20555                                                 !
King of Prussia, PA 19406 Mr. Victor Herses, Project Manager l
l NRC Senior Resident Inspector                                       l P.O. Box 1149 l                     Seabrook, NH 03874 l                                                                                         >
Project Directorate I-3 j
l                                                                                         1 1
l United States Nuclear Regulatory Commission l
I i
Division of Reactor Projects l
i Washington, DC 20555 l
NRC Senior Resident Inspector l
P.O. Box 1149 l
Seabrook, NH 03874 l
l 1
1 I
i i
i i
l l
i l
                                                                        , _ . .}}
l
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Latest revision as of 07:44, 23 December 2024

Provides Currently Available Info Re Subj of in-core Instrumentation Thimble Thinning.Util Planning to Provide Requested Response to NRC Bulletin 88-009 Following Completion of First Refueling Outage
ML20005G748
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 01/11/1990
From: Feigenbaum T
PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-88-009, IEB-88-9, NYN-90010, NUDOCS 9001230028
Download: ML20005G748 (2)


Text

.

t '

v: y New Hompshire?

o m.,

Senior Vice President and '

Chief Operating Officer l

NYN-90010

)

January 11, 1990 United States Nuclear Regulatory Commission Washingtoni DC-20555 a

Attention: Document Control Desk i

References:

(a). Facility Operating License NPF-67,. Docket No. 50-443' l

(b) NRC Bulletin 88-09. dated' July 26, 1988, " Thimble Tube.

I L

l Thinning-in Westinghouse Reactors' i

Subject Information Regarding Incore Instrumentation Thimble Thinning' L

Gentlemen:

i This letter provides currently-available information regarding.the

(

subject of incore instrumentation ' thimble thinning as it' applies to Seabrook l

Station.

New Hampshire Yankee.(NHY) is planning to-provide the requested i

response to NRC Bulletin 88-09 following completion of the first). refueling i

outage of Seabrook Station Unit 1 in accordance with.the schedule specified i

by the Bulletin.

The Seabrook Station fixed / movable incore instrumentation system features a unique mechanical design which provides in-depth protection,against. reactor coolant leakage consequent to thimble wear. The'in-core instrumentation l

thimble contains fis:ed detectors. Consequently, the design Includes two concentric thimbles.

The inner thimble permits the moveable = detector'to l

traverse the core and serves as the reactor: coolant pressure-boundary.- The l

outer thimble serves as the housing for the fixed incore'detectoru and incore thermocouples, which are located between the inner and outer

~

thimbles.

Failure of the outer thimble would not breach the reactor coolant-pressure boundary.

Failure of both outer and inner thimbles would'be required to breach-the reactor coolant pressure' boundary. -In the.h_ighly s

unlikely event of a wear-induced failure of both inner and outer thimbles, isolation valves at the seal table can be used to terminate reactor = coolant leakage.

New Hampshire Yankee expects to develop.n inspection program to monitor thimble performance.

The program will 'e based, in part, upon industry experience and' vendor recommendations.

The program will'be-implemented at'

..I the first refueling outage of Seabrook Station Unit 1.

The report 6

confirming that the program has been established and that the initial thimble inspections have been performed in accordance with the requirements of the program will be submitted within thirty (30) days of completion of the inspections.

[

9001230028 900111 F

PDR ADOCK 05000443

/

Q PDC New Hampshire Yonkee Division of Public Service Company of New Hampshire (p

i P.O. Box 300

  • Seabrook, NH 03874
  • Telephone (603) 474 9521 -

I, United States. Nuclear Regulatory Commission January 11, 1990-Attention: Document Control Desk Page 2.

L If you have any questions on this matter please contact Mr. Geoffrey

[

Kingston at (603) 474-9521..

Very truly yours, h&f 4 L

Ted C. Feigenbaum j

cc:

Mr. William T. Russell l.

Regional Administrator l

United States Nuclear Regulatory Commission Region I l

475 Allendale Road l

King of Prussia, PA 19406 Mr. Victor Herses, Project Manager l

Project Directorate I-3 j

l United States Nuclear Regulatory Commission l

Division of Reactor Projects l

i Washington, DC 20555 l

NRC Senior Resident Inspector l

P.O. Box 1149 l

Seabrook, NH 03874 l

l 1

1 I

i i

i l

l

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