A09659, Submits Response to Review of RI-91-A-0148 Issues Concerning Plant Activities

Submits Response to Review of RI-91-A-0148 Issues Concerning Plant Activities

ML20091E092
Person / Time
Site:	Millstone
Issue date:	08/16/1991
From:	Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO.
To:	Hehl C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20091E089	List: A09556, Submits Response to Review of RI-91-A-0037 Issues Concerning Plant Activities A09559, Submits Response to Review of RI-91-A-0052 Issues Concerning Plant Activities A09569, Submits Response to Review of RI-91-A-0063 Issues Concerning Plant Activities A09604, Submits Response to Review of RI-91-A-0082 Issues Concerning Plant Activities A09657, Submits Response to Review of RI-91-A-0118 Issues Concerning Plant Activities A09658, Submits Response to Review of RI-91-A-0137 Issues Concerning Plant Activities A09659, Submits Response to Review of RI-91-A-0148 Issues Concerning Plant Activities A09660, Submits Response to Review of RI-91-A-0069 Issues Concerning Plant Activities A09661, Submits Response to Review of RI-91-A-0145 Issues Concerning Plant Activities A09700, Submits Response to Review of RI-91-A-0093 Issues Concerning Plant Activities A09716, Submits Response to Review of RI-91-A-0143 Issues Concerning Plant Activities B13905, Submits Response to Review of RI-91-A-0064 Issues Concerning Plant Activities B13926, Provides Response to Investigation Concerning RI-91-A-0137 Issues Concerning Plant Activities
References
A09659, A9659, NUDOCS 9110310042
Download: ML20091E092 (3)

Text

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.,,. H AATFORD. CONNECTICUT 06141-0270 (203) 665 5000 August 16, 1991 Docket No. 50-336 A09659 RE: Employee Concerns Hr. Charles V. Behl, Director Division of Reactor Projects U. S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, Pennsylvania 19406

Dear Mr. Behl:

Hillstone Nuclear Power Station, Unit No. 2 RI-91-A-0148 Ve have completed our review of identified issues concerning activities at Hillstone Station.- As requested in your transmittal letter, our response does not contain any personal privacy, proprietary, or safeguards

-information. The material contained in these responses may be released to the public and placed in the NRC Public Document Room at your discretion.

The NRC letter and our response have received controlled and limited distribution on a "need to know" basis durirg the preparation of this response.

ISSUE 1:

On Juna 14,- 1991, while attempting to replace the " Seal Tite" flexible electrical conduit and the position indicator vindow for No. 1 Steam Generator Main Steam Isolation Bypass Valve motor operator (2-MS-65A), it was found that the work had been done previously under AVO H2-89-01828 on March 13, 1989. However, the prints had not been updated.

Please discuss the validity of the above assertions. If deficiencies in vork control or drawing control are founj, please inform us of the corrective actions you have taken to prevent recurrence. Please provide us with sn assessrant of the significance with regard to safety of any identified deficiencies.

Response: -

Automated Vork Order (AVO) H2-90-13990 was written to govern replacement of damaged SealTite on 2-MS-65A. The AVO also specified that any vire which had to be disconnected be reterminated in accordance with EE0 requirements.

Upon inspection of the junction to which the SealTite was Attached, it was found that the Sea 1 Tite contained no vires. The damaged SealTite was removed and plugs installed in the conduit entrance to 'he junction box and the MOV.

9110310042 911011 '

PDR ADOCK 05000336~

@. _ .PDR_ _ .. . _ - - _ _ _ _ _ - - _ _ _ _ - _ -

l Mr. Ch rics V. 5;hl, Dirceter .

U. S. Nuclear Regulatory Commission A09659/Page 2 August 16. 1991 ,

. i AVO M2-89-01828 should be AVO M2-89-04828 vhich was completed in April - l

1989. This work order governed replacement of the viring and damaged j SealTite associated with 2-M?-65A.- This is not the AVO that was -used to govern removal of the vires from the SealTite described above. No draving change was required as a result of this AVO.-

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The vires to the position indicator vere removed under AVO M2-90-13178 vhich was completed on November 2, 1990. This AVO implementw ?lant Design Change Record (PDCR) 2-055-90,- Removal of Slide Virc Potentiometers L

Providing- Indication for Main Steam Bypass Valves 2-MS-65A li B. The SealTite associated with these wires was abandened in place. A drawing

!; change request, DCR M2-P-189-90.vas written to up6 ate applicable electrical drawings affected by this change. The DCR vas closed out on February 12, 1991.

1 1 The assertion described in Issue 1 above is not valid. -The work performed l

on 2-MS-65A vas properly authorized and documented in the AV0s and a PDCR. j

! Vhen the vork vas completed, the as-built conditions were properly '

documented through a drawing change request and. drawing revisions.- l l ISStIE 2:

On June.14, 1991, differences between a control viring diagram and actual plant conditions were found.. The-viring diagram (Draving 25203-32020) for the No.1 Steam Generator _ Main Steam Bypass Valve (2-MS-65A) Motor Operator q f indicates the presence of an amber . light to signify when the unit has

[ -tripped on overload. This light is not installed.

l Also, Contact'49, shovn on Drawing 25203-3203), Sheet 42 does not exist.

1 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

l. 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 oc the drawing. The . drawing 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 drawing vill be issued at an as-built iraving.

l-NUSCO Draving 25203-32031, Sheet 42 is a new drawing 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 drawings have been issued for construction, which is clearly indicated on the dreving.

Field 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. Charl:s V. H:hl, DirGetor

_ U. S. Nucloor R gulatcry Ccamission

_A09659/Page 3 August /16,~1991-After. our review and evaluation, we find that this issue does not present l any indication of a compromise of nuclear safety. Issues such as these are normally handled via our corrective actions prograss. Ve were 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 satters.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY FOR: E. J. Mroczka Senior Vice President BY:

V. D. Romberg(s' Vice President cc: V. - J. Raymond, Senior Resident- Inspector, Millstone Unit Nos. 1, 2, and 5  ;-

E. C. Wenzinger, Chief, Projects Branch No. 4, Division of Reactor

. Projects E. M. Kelly, Chie,f, Reactor Projects Section 4A i

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