A09829, Informs That Review of Issues Re Facility Activities for Allegation RI-91-A-0210 Complete.Comments Encl

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Informs That Review of Issues Re Facility Activities for Allegation RI-91-A-0210 Complete.Comments Encl
ML20091P995
Person / Time
Site: Millstone Dominion icon.png
Issue date: 09/30/1991
From: Mroczka E
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To: Hehl C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20091P903 List:
References
A09829, A9829, NUDOCS 9202040124
Download: ML20091P995 (3)
v • d • e


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i NORTHEAST UTILTTIES o.n,<.i on.c. . see a su i. 8.<i.a. cona.ci.cui t .

, )E September 30, 1991 Docket No. 50 331 69E12 Mr. Charles W. Hehl, Director Division of Reactor Projects U.S. Nuclear Regulatory Commission Region i 475 Allendale Road King of Prussia, PA 19406

Dear Mr. Hehl:

Millstone Nuclear Power Station, Unit No. 2 RI-91-A 0210 We have completed our review of an identified issue 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 this response may be released to the public and placed in the NRC Public Document Room at your discretion. The NRC transmittal letter and our response have received controlled and limited distribution on a "need-to know" basis during the preparation of this response.

ISSUE 210 1:

" Millstone 2 turbine sampling system valws with a prefix of '2 S' are not -

labeled in the field, in addition, the sodium analyzer 'AE 7764 A5', is incorrectly labeled as 'AE 7764 A6' on sheet 3 of drawing 25203 26025."

RE0 VEST:

"Please discuss the validity of the above assertion, if the above conditions are valid, please notify us why this was not previously corrected by your labeling program and what corrective actions you have taken to prevent recur-rence. Please provide us with an assessment of the safety significance of any identified deficiencies, including any generic considerations."

RJSPONSE 210-1:

The assertion concerning the sampling system valve labels is valid if the stated analyzer is AE7784 rather than AE 7764. We were made aware of the drawing problem in early September, 1991. The Millstone Unit No. 2 Engineering Department has identified that the Piping and Instrument Diagram (P&lD) does not agree with the as-built condition and is in the process of updating the drawings to reflect the as-built conditions.

9202040124 911106 l PDR ADOCK 05000336 '

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l Mr. Charles W. Hehl A09829/Page 2 September 30, 1991 In March 1991, a new Administrative Control Procedure, ACP-6.22--System and Component labeling was written and issued to provide guidance on a standard-ized labeling program for the Millstone site. Also in March, a Controlled Routing (CR 8139) was issued to track the progress of each of the units in complying with the requirements of the ACP. The labeling effort includes valves, major components, and instrument and gauge labeling. The sampling

'J3 tem valves identified in the assertion are part of this program. The valve labeling efforts are expected to be completed by the end of 1992. Currently the Operations Department is holding discussions with other departments in the unit in an effort to establish who will normally operate and be responsible for labeling valve *, such as those associated with radiatio" monitors, sample systems, etc.

As part of the program implemented under ACP 6.22 a label request form has been generated which allows anyone finding a missing, incorrect, or deterio-rating label to bring it to the attention of the label coordinator or Opera-tions Manager for prompt action.

As part of the labeling program under ACP-6.22, the initial labeling of a system is to be verified by a complete walkdown of the system using system ,

checklists and P&lDs to determine that all system components are labeled and that the label nomenclature matches the P&lD identification and system check-list description for each component. Thus, if other similar problems exist, they should be routinely identified and corrected as part of this program.

ISSUE 210-2:

" Circuit changes had l'een made to the Millstone 2 main generator hydrogen "p monitor without the preparation of a modif' cation package. As a re; ult, the calibration procedure is inadequate, and appropriate procedure and 6 awing changes have not made."

RE0 VEST:

"Please discuss the validity of the above assertion. If the above conditions are val id , please notify us of the corrective actions you have taken to prevent recurrence. Please provide us with an assessment of the safety signi-fic mce of any identified deficiencies, including any generic considerations."

RESPONSE

We are still investigating this matter and will respond when the investigation is complete. We currently plan to respond by October 14, 1991.

Mr. Charles W. Hehl A09829/Pa9e 3 September 30, 1991 After our review and oveluation of this issue, we find that it did not present any indication of a compromise of nuclear safety. We appreciate the opportu-ri y to respond and explain the basis of our actions. Please contact my staff if there are further questions on any of these matters.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

$dW< AfW L wa.yf J. Hroc a Senitr Vice President cc: W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2, and 3 E. C. Wenzinger, Chief Projects Branch No. 4 Division of Reactor Projects E. M. Kelly, Chief, Reactor Projects Section 4A J. T. Shedlosky, U.S. Nuclear Regulatory Commission, Hillstone l

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