ML20036B463

From kanterella
Jump to navigation Jump to search
Partially Deleted Ltr Addressing Two Concerns Provided to NRC on 910617,alleging Lapse in Control of Work on safety- Related Equipment & That Control Wiring Diagram for One Operator Does Not Agree W/Plant as-built Conditions
ML20036B463
Person / Time
Issue date: 10/28/1991
From: Wenzinger E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
AFFILIATION NOT ASSIGNED
Shared Package
ML20036A053 List:
References
FOIA-92-162 NUDOCS 9305200267
Download: ML20036B463 (4)
v • d • e


Text

-

'c, UNa[D STATES NUCLEAR REGULATORY COMMISSION

! ' ),,

g r

RE GioN I i

9 a'

C5 ALLENDALE ROAD

{

o,

~

e KING OF PRUsStA, PENNSYLVANIA 19406 1415 g*"**j OCT 2 81991 This letter refers to two concerns that you provided to us on June 17,1991, alleging that there was a lapse in the control of work on safety-related equipment, and that the control wiring i

diagram for one safety-related valve motor operator does not agree with plant as-built conditions.

Dese concerns were referred to Northeast Utilities for their review. Attached for your information are their responses, dated August 16, 1991. Our assessment of your concerns are that additional Automated Work Orders and Document Change Requests, listed by the Licensee, properly documented the work on the safety-related equipment, and that drawings modified for construction are expected to reflect as-built conditions.

Therefore, the NRC plans no further action in these matters, and we consider these concerns closed.

We appreciate you informing us of your concerns and feel that we have been responsive. Should you have any additional questions regarding these matters, please call me collect at (215) 337-5225.

Sincerely, J$ './ $ h Edward Wenzinger, C ~ (

Reactor Projects Br h3

Enclosures:

NU Letter of August 16,1991 (File No. 91-0148)

Ir.!nm:Sn in l'.is rctnd ',cs dd in Ltcacnte v,th the freedcm ci trdorraation t.tt, cxtradcs dI2

-- - ~

E01 A __f-_2 - /4 >-

,I y[

9305200267 930216 "i !

(}

PDR FOIA HUBBARD92-162 PDR k

(

2 4

I RI-91-A-0]148 i

bec:

)

Allegation file, E. Conner files, j

E. Kelly (Secdon Chief)

W. Raymond T. Mediosty Contractor's office files (MEEKER)

RI:DRP i

l

\\

concurrences:

RI:DRP 1:DRP R

RP Of l7s '

\\V nzinger f

onner ay Id@$

[p/ k' g/lh

3

]

pa 'ic

/

.- /

g%

P )(

UNiTEo STATES 8

?%

NUCLEAR REGULATORY COMMISSION b,,, 7 i

REGION i 475 ALLEN 0 ALE RoAo f

> ib o

xisc or raussiA. etNssytvAsiA iserri4is g *.

- j-OCT 2 81991 This letter refers to two concerns that you provided to us on June 17,1991, alleging that there was a lapse in the control of work on safety-related equipment, and that the control wiring diagram for one safety-related valve motor operr-tor does not agree with plant as-built conditions.

These concems were referred to N;rtheast Utilities for their review. Attached for your information are their responses, dated August 16, 1991. Our assessment of your concerns are that additional Automated Work Orders and Document Change Requests, listed by the Licensee, properly dccumented the work on the urety-related equipment, and that drawings mcditbi for construction are exyted to ref'xt as-built conditions.

j Act

[d4 "

Therefore, the NRC plans no further action in these matters, and we consider these concerns f

closed.

We appreciate you informing us of your concerns and feel that we have been responsive. Should you have any additional questions regarding these matters, please call me collect at (215) 337-5225.

1 Sincerely, i

- f 19 9

s Edward Wenzinger, C Reactor Projects Brandh A L

Enclosures:

NU Letter of August 16,1991 (File No. 91-0148)

\\

.in!=3:!:n in th.s record was ceyes n 2 :ctdance w,th the freedom of infortnation A;t,cxe as __dM 7 C f;

FO! A._

_ - /4 z -

/

l bec:

Allegation file, RI-91-A-0148 E. Conner files.

E. Kelly (Secdon Chief)

W. Raymond T. ShWlosky Contractor's office files (MEEKER) l RI:DRP 1

l l

1 i

1 i

4 l

l a

i concurrences; RI:DRP I:DRP e

+

onner

.y Wcnzinger u_' d f jp//1'

[l[/h i

l i

~

NORTHEAST UTILtTIES c.n... on.cn s.ic.a sir i. s.mn. cona.ci.ca i

1 ro c,ew c.ome tw=

P O. BOX 270 HARTFORD. CONNECT

  • CUT 06141 c270

.i e.icac s--

a ws"o== s**"

==.:::

om * **

t a

August 16, 1991 Docket No. 50-336 A09659 i

RE: Employee Concerns Mr. Charles V. Behl, Director Division of Reactor Projects U. S. Nuclear Regulatory Commission Region I 475 Allendale P.oad King of Prussia, Pennsylvania 19406

Dear Mr. Behl:

Millstone Nuclear Power Station, Unit No. 2

-RI-91-A-0148 have completed our review of identified issues concerning activities at VeMillstone Station. As requested in your transmittal letter, our response any personal privacy, proprietary, or safeguards does not contain The caterial contained in these responses may be released to information.

Document Room at your discretion.

the public and placed in the NRC Public The NRC letter and our response have received controlled and limited distribution on a "need to know" basis during the preparation of this response.

ISSUE 1:

On June 14, 1991, while attempting to replace the " Seal Tite" flexible electrical conduit and the position indicator vindow for No.

1 Steam Main Steam Isolation Bypass Valve motor operator (2-MS-65A), it Generator found that the work had been done previously under AVO M2-89-01828 on was March 13, 1989. Bovever, the prints had not been updated.

Please discuss the validity of the above assertions. If deficiencies in vork control or drawing control are found, please inform us of the Please provide us corrective actions you have taken to prevent recurrence.

with an assessment of the significance with regard to safety of any identified deficiencies.

Response

Automated Vork Order (AVO) M2-90-13990 vas written to govern replacement of ~

SealTite on 2-MS-65A. The AVO also specified that any vire which damaged had to be disconnected be reterminated in accordance with EE0 requirements.

inspection of the junction to which the SealTite was attached, it was Upon found th t the SealTite contained no vires.

The damaged SealTite was removed and plugs installed in the conduit entrance to the junction box and the MOV.

g

\\

flo Y00 @

\\

s Mr. Ch:rles V. Eshl, Director U. S. Nuclear R:gulatory Commissien A09659/Page 2 August 16, 1991 AVO M2-89-01828 should be AVO M2-89-04828 which was completed in April 1989.

This work order governed replacement of the viring and damaged SealTite associated with 2-MS-65A. This is not the AVO that was used to removal of the vires from the SealTite described above. No drawing govern change was required as a result of this AVO.

The vires to the position indicator vere removed under AVO M2-90-13178 vhich was completed on November 2, 1990. This AVO implemented Plant Design Change Record (PDCR) 2-055-90, Removal of Slide Vire Potentiometers Providing Indication for Main Steam Bypass Valves 2-MS-65A &

B.

The SealTite associated with these vires was abandoned in place. A drawing DCR M2-P-189-90 was vritten to update applicable electrical change request, dravings affected by this change. The DCR vas closed out on February 12, 1991.

The assertion described in Issue 1 above is not valid. The work performed 2-MS-65A vas properly authorized and documented in the AV0s and a PDCR.

on When the vork vas completed, the as-built conditions vere properly documented through a drawing change request and draving revisions.

ISSJE 2:

On June 14, 1991, differences between a control viring diagram and actual plant conditions vere found. The viring diagram (Draving 25203-32020) for the No. 1 Steam Generator Main Steam Bypass Valve (2-MS-65A) Motor Operator indicates the presence of an amber light to signify when the unit has tripped on overload. This light is not installed.

Also, Cor. tact 49, sh:vn on Draving 25203-32031 Sheet 42 does not exist.

Please discuss the validity of the above assertions. If deficiencies are found in plant drawings, please notify us if the corrective actions tak.en to prevent recurrence.

Please provide us with an assessment of the significance with regard to safety of any identified deficiencies.

Response

NUSCO Draving 25203-32020 was revised in support of Project Assignment (PA)

No.84-063 and has been issued for construction, which is clearly marked on the draving. The draving is intended to be used to support the viring changes required by PA No.84-063 and is not intended to reflect the current as-built condition. The contact vill be added in the field when the viring changes required by P.A.

No.84-063 are completed. Upon completion of the design change, the as-built condition vill be verified and the draving vill be issued as an as-built draving.

NUSCO Draving 25203-32031, sheet 42 is a new draving generated to support implementation of PA No.84-063. This drawing has also been issued for.

construction.

The assertion described in Issue 2 above is not valid. The dravings have been issued for construction, which is clearly indicated on the drawing.

Field changes have not yet been completed to install the contact. There are no deficiencies in the plant dravings and no adverse impact on plant safety.

Mr. Charles V. 5:hl, Director U. S. Nuclear Regulatory Commissisn A09659/Page 3 August 16, 1991 After our review and evaluation, we find that this issue does not present Issues such as these are j

any indication of a compromise of nuclear safety.

Ve were not aware of normally handled via our corrective actions programs.

these concerns prior to receipt of the Staft's letter. We appreciate the l

i opportunity to respond and explain the basis of our actions.

Please contact ry staff if there are any further questions on any of these matters.

I Very truly yours.

l i

NORTHEAST NUCLEAR ENERGY COMPANY 1

i I

FOR:

E. J. Mroczka i

Senior Vice President t

]

I i

BY:

V. D. Rombergg5' Vice President l

i i

cc:

V.

J. Raymond, Senior Resident Inspector, Millstone Unit Nos.

1, 2, i

and 3 E.

C. Venzinger, Chief, Projects Branch No.

4, Division of Reactor j

Projects E. M. Kelly, Chief, Reactor Projects Section 4A i

I i

i i

I l

i i

J l

i I

i d

?

i i

1

.. ~.

M M W El0 G:ners: Othces

5,7EYiSNw P O. BOX 270 HARTFORD. CONNECTICUT 06t41-0270 e m w =* **

5'?,",C",".T. "~

(2c33 ass som L

a August 16, 1991 Docket No. 50-336 A09659 RE: Employee Concerns Mr. Charles V. Behl, Director Division of Reactor Projects i

U. S. Nuclear Regulatory Commission l

Region I 475 Allendale Road King of Prussia, Pennsylvania 19406

Dear Mr. Behl:

Millstone Nuclear Power Station, Unit No. 2 RI-91-A-0148 have completed our review of identified issues concerning activities at Millstone Station. As requested in your transmittal letter, our response Ve any personal privacy, proprietary, or safeguards l

contain does not The material contained in these responses may be released to information.

the public and placed in the NRC Public Document Room at your discretion.

  • e NRC letter and our response have received controlled and limited distribution on a "need to knov" basis during the preparation of this response.

ISSUE 1:

On June 14, 1991, while attempting to replace the " Seal Tite" flexible electrical conduit and the position indicator vindow for No.

1 Steam Main Steam Isolation Bypass Valve actor operator (2-MS-65A), it Generator was found that the work had been done previously under AVO M2-89-01828 on March 13, 1989. Bovever, the prints had not been updated.

Please discuss the validity of the above assertions.

If deficiencies in verk control or draving control are found, please inform us of the i

Please provide us corrective actions you have taken to prevent recurrence.

i with an assessment of the significance with regard to safety of any identified deficiencies.

Response

Automated Vork Order (AVO) M2-90-13990 vas written to govern replacement of ~

Sea 1 Tite on 2-MS-65A. Thc AVO also specified that any vire which damaged had to be disconnected be reterminated in accordance with EE0 requirements.

inspection of the junction to which the SealTite was attached, it vas Upon found that the SealTite contained no vires.

The damaged SealTite was removed and plugs installed in the conduit entrance to the junction box and the MOV.

hr

'D Y 0 0 t'"ll,

\\

Mr. Charls: V. B;hl, Dirceter U. S. Nuclear Regulatory Coaaissien v

A09659/Pega 2 August 16, 1991

(

AVO M2-89-01828 should be AVO M2-89-04828 vhich vas completed in April 1989.

This work order governed replacement of the viring and damaged SealTite associated with 2-MS-65A.

This is not the AVO that was used to govern removal of the wires from the SealTite described above. No drawing change was required as a res.it of this AVO.

The vires to the position indicator vere removed under AVO M2-90-13178 vhich was completed on November 2, 1990. This AVO implemented Plant Design Change Record (PDCR) 2-055-90, Removal of Slide Vire Potentiometers Providing Indication for Main Steam Bypass Valves 2-MS-65A fi B.

The SealTite associated with these vires was abandoned in place. A draving change request, DCR M2-P-189-90 was written to update applicable electrical dravings affected by this change. The DCR vas closed out on February 12, 1991.

The assertion described in Issue 1 above is not valid. The work performed 2-MS-65A vas properly authorized and documented in the AV0s and a PDCR.

on Vhen the work vas completed, the as-built conditions were properly documented through a drawing change request and drawing revisions.

ISSUE 2:

On June 14, 1991, differences between a control viring diagram and actual plant conditions vere found. The viring diagram (Drawing 25203-32020) for the No. 1 Steam Generator Main Steam Bypass Valve (2-MS-65A) Motor Operator indicates the presence of an amber light to signify when the unit has tripped on overload. This light is not installed.

Also, Contact 49, shovr. on Draving 25203-32031, Sheet 42 does not exist.

Please discuss the validity of the above assertions. If deficiencies are found in plant drawings, please notify us if the corrective actions taken to prevent recurrence.

Please provide us with an assessment of the significance with regard to safety of any identified deficiencies.

l

Response

NUSCO Draving 25203-32020 vas revised in support of Project Assignment (PA)

No.84-063 and has been issued for construction, which is clearly marked on the draving. The draving is inte_nded to be used to support the viring

~

changes required by PA No.84-063 and is not intended to reflect the current as-built condition. The contact vTITTe added in the field when the viring changes required by P.A.

No.84-063 are completed. Upon completion of the design change, the as-built condition vill be verified and the draving vill be issued as an as-built drawing.

NUSCO Draving 25203-32031, Sh= t 42 is a new draving generated to support i

implementation of PA No.84-063. This drawing has also been issued for -

1 construction.

The assertion described in Issue 2 above is not valid. The drawings have been issued for construction, which is clearly indicated on the draving.

I Pield changes have not yet been completed to install the contact. There are no deficiencies in the plant drawings and no adverse impact on plant safety.

Mr. Ch2rics V. Behl, Dirceter U. S. Nucl ar R';gulatory C':rmissicn A09659/Pega 3 August 16, 1991 After our review and evaluation, ve find that this issue does not present any indication of a compromise of nuclear safety. Issues such as these are normally handled via our corrective actions programs. Ve vere not aware of these concerns prior to receipt of the Staff's letter. Ve appreciate the opportunity to respond and explain the basis of our actions. Please contact my staff if there are any further questions on any of these matters.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPJJU f

FOR:

E. J. Mroczka Senior Vice President BY:

V. D. Romberg(/

Vice President ec:

V.

J. Raymond, Senior Resident Inspector, Millstone Unit Nos.

1, 2, and 3 E.

C. Venzinger, Chief, Projects Branch No.

4, Division of Reactor i

Projects E. M. Kelly, Chief, Reactor Projects Section 4A

?

Retrieved from "https://kanterella.com/w/index.php?title=ML20036B463&oldid=4572494"