ML20036B450
| ML20036B450 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/28/1992 |
| From: | Wenzinger E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | AFFILIATION NOT ASSIGNED |
| Shared Package | |
| ML20036A053 | List:
|
| References | |
| FOIA-92-162 NUDOCS 9305200126 | |
| Download: ML20036B450 (2) | |
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NUCLEAR REGULATORY COMMIS$10N g
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475 ALLENDALE ROAD STg[
e EING oF PRUSSLA, PENNSYLVANIA 194 5 1415 i
713 2 81992 I am responding to the concerns that you provided to us on July 29,1991, asserting that the Millstone Unit 2 senice water system was placed in operation without the completion of all post maintenance tests associated with a plant design change modification (PDCR).
We have inspected this concern; a report with the results of that inspection is attached for your information. Based on our inspection we have determined that the senice water system was returned to operation prior to the completion of all applicable tests associated with PDCR 2-057 90. Northeast Utilities (NU) is evaluating their Administrative Control i
Procedure (ACP) ACP-QA-3.10 to clarify the documentation and testing requiremes.ts associated with short form PDCRs. Since senice water system operability was not materially affected, no further action is planned by the NRC in this matter, and we consider this concern to be resolved.
We appreciate you informing us of your concerns and feel that we have been responsive.
Should you have any additional questions regarding these matters, please call me collect at (215) 337-5225.
J Sincerely, j
tt Edw d Wenzinger, C aef j
Reactor Projects Bra, ch 4 l
l
Attachment:
Excerpts from NRC Inspection Report 50-336/91-31 (Detail 2.0).
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. ~ _, ~ --.. - 2 s [,... r 'c. UNITED sTAf ts ' j NUCLEAt1 REGULATORY COMMISSION E g a ftt GON I 475 ALLENDAtt ROAD l e "r t.ING of PRuss6A. PENN$YLVANia 19436 1415 I Docket No. 50-336 EB 2 4 N Mr. J. Opeka l Executive Vice President - Nuclear j 4 Nonheast Nuclear Energy Company l P.O. Box 270 j Hanford, Connecticut 06141-0270 l 1 I l
Dear Mr. Opeka:
I J
Subject:
NRC Region I Inspection Report No. 50-336/91-31 y Mr. J. T. Shediosky and others of this office conducted a special safety inspection December 17, 1991, through February 7,1992, at the Millstone Nuclear Station Unit 2. Waterford, i Connecticut. ne inspection results are documented in the enclosed report. ney were j discussed with Mr. J. S. Keenan and other members of your staff at the conclusion of the inspection. l Areas examined during the inspection are described in the enclosed report. Within these areas, f the inspection focused on issues brought to Northeast Utilities by the NRC. Our independent l review evaluated your performance in complying with regulatory requirements imponant to j public and worker health and safety. This review consisted of performance observations of j ongoing activities, inspection of plant equipment, interviews with personnel, and review of l records. Our overall assessment was that performance was acceptable. De enclosed inspection repon notes a number of issues on which your staff agreed to provide a response to the NRC. j NNECO's response to the NRC may be made in communication with the resident inspectors. l i in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and l its enclosures will be placed in the NRC Public Document Room. De responses directed by this letter are not subjected to the clearance promdures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, Public law No. %.511. i l Your cooperation with us is appreciated. l S' y, t j Edward C. % g r Chief Projects Branch No. 4 { j Division of Reactor Projects E I l J \\ i \\ N i -- [L2-D h h i ....,,r, ..._,_,._,....__.._.m.
t. FEB 2 4 892 Northeast Nuclear Energy Company 2 ~
Enclosure:
NRC Region i Inspection Report No. 50-336/9131 l cc w/ enclosure: 4 W. D. Romberg, Via President, Nuclear Operations D. O. Nordquist, Director of Quality Services R. M. Kacich, Manager, Nuclear Licensing S. E. Scaz, Nuclear Station Director, Millstone J. S. Keenan, Nuclear Unit Director, Millstone Unit 2 l Gerald Garfield, Esquire Nicholas Reynolds, Esquire. K. Abraham, PAO (2) Public Document Room (PDR) i Imal Public Document Room (LPDR) Nuclear Safety information Center (NSIC) NRC Resident inspector State of Connecticut l u b I 1 [ l I t i l l \\
I l 4 Conclusion When the replacement switch identification error was detected, the technicians referred to l available documentation and obtained the correct switch. De technicians made an initial procurement mistake, but correctly resolved the problem. He incorrect switch was never installed in this non-safety-related system. 1 2.0 SERVICE WATER SYSTEM PDCR 2-457-90 The NRC provided a concern related to a plant design change request (PDCR) for installation j of a sample valve and "T* fitting on the service water (SW) strainer differential pressure (D/P) l instrument tubing at MP2. For reference, inspection Reports 50-336/91-20 (section 6.2) and 50-336/91-28 (section 6.4) described the NRC's review of NNECO's MP2 SW system biofouling } protection program. Assessment 1 De SW system is a safety related fluid system that supplies cooling water (sea water) to the { emergency diesel generators, the reactor building closed cooling water system heat exchangers, and the turbine building closed cooling water system heat exchangers. Dere are three 50% i capacity SW pumps rated at 12,000 gpm each. At the discharge of each pump, there is a 24' l automatic self-cleaning strainer. Each strainer has D/P monitoring instrumentation that initiates strainer backwash and provides a differential pressure alarm. The purpose of (short form) PDCR 2-057-90 was facilitation of SW system sampling for chlorine content. Implementation and testing of PDCR 2-057-90 was donc per work order AWO M2-90-15617. To reduce biological fouling, a sodium hypochlorite system chlorinated the SW i system. PDCR 2-057-90 involved addition of a tee fitting, a 1/4" Whitey valve, and associated instrument tubing in the 1/4" SW strainer D/P instrument tubing for each strainer. The new j sample valves were numbered 2-SW-276A, B, and C. PDCR 2-057-90 included a safety j evaluation that concluded 'this design change is safe and does not constitute an unreviewed safety question as defined in 10CFR50.59.* MP2 Technical Specification 3/4.7.4 required SW operability in modes 1,2, 3, and 4. Prior to work approval, as required by ACP-QA 2.02C, section 6.5, the Senior Control Room Operator (SCO) determined installation of PDCR 2-057-90 in accordance with AWO M2 15617 did not affect SW operability. i The test plan in PDCR 2-057-90 required in-service leak testing (which m2s done on December 13,1990) for the completed installation of sampling valves 2-SW-276A and B. Because the 'C' j SW strainer was unavailable at that time, NNECO deferred in-service leak testing of sampling valve 2-SW 276C. l 1 l i i
\\ 5 i* ACP-QA-2.02C, revision 25, section 6.12, assigned responsibility for overall implementation j and testing of plant modifications to the Plant Engineer. ACP-QA-2.02C, section 6.12.5, required (in part) that before a system or component may be declared operable and accepted by Operations, the Plant Engineer must verify that applicable administrative requirements of ACP-QA-3.10 have been met. ACP-QA-3.10, Attachment 1, section 6.1, required (in part) completion of
- applicable administrative impact items
- and evaluation of other required administrative updates such as the examples listed on a PDCR (Form B).* Although not listed as an " administrative impact item" or
- administrative update," Item 13D in Form B required completion of construction and pre-operational testing.
hWECO closed PDCR 2457-90 on January 19, 1991. NNECO completed in service leak testing of 2-SW-276C on August 13, 1991 and closed AWO M2-90-15617 on September 12, 1991. Conclusions Based on discussions with cognizant NNECO personnel, physical inspection of the equipment in question, and review of relevant documentation, the inspector concluded the following: because NNECO closed PDCR 2-057-90 prior to completion of the testing specified in AWO M2-90-15617, in this instance there was inadequate attention to detail in compliance with applicable administrative control procedures. Further, requirements for completion of all necessary work documents and testing were not clearly promulgated by ACP-QA-3.10 for short form PDCRs. NNECO agn:ed to evaluate opportunities for improvement in ACP-QA-3.10 (that would help ensure completion of work dccuments and te' ting prior to PDCR closures), take s appropriate action as necessary, and respond to the hTC. Also, based on the preceding assessment and review of the PDCR 2457-90 safety evaluation, the ins;xrtor concluded that closure of PDCR 2-057-90 prior to closure of AWO M2-90-15617 did not materially affect SW system operability. 3.0 RADIATION MONITOR DRAWINGS 'Ile NRC provided concerns to NU related to certam procedures and a plant design change (PDC) for radiation monitoring equipment at MP2. NRC disposition of those concerns involved providing the concerns to NNECO for review and resolution, with subsequent'NRC evaluation to ensure the adequacy of NNECO's actions. NNECO letter A09559, dated August 9,1991, described NNECO's review of those concerns. 3.1 PDCR M2-90 032 During implementation of PDCR MP2-90432 in early 1991, NNECO found some discrepancies between drnwing 25203-39092, sheet 14C, and the as-built status of equipment. l I
- 2. h
~ ALLEMTION RECEIPT REPDRT i - l4 l Date/ Tine [vas k /M/ 7#b Allegation No. /f.[ #ll-A - / 3 7 Received: (Jy Agno bargo 4/3 \\enve blant. Name: Address: Phone: City / State / Zip j 3 Confidentiality: j k'as it requested? Yes No > k'as it initially granted? Yes No Vas it finally granted by the allegation panel Yes No Does a confidentiality agreement need to be sent j to alleger? Yes No i Has a confidentiality (greement been signed? Yes No i Memo cocumenting why it was granted is attached? Yes No i Allecer's l Em:1cyer:' /4 7 6 >- Fosition/ Title i i i l Facility: Muc.f reu r Up sr 2 Docket No.: f0336 (Allegation Summary (brief description of concern (s): Nereuvn 8mry DeGG /MG G~Ano/t. [L sc 771t L/RN I?t SC cW6r160 l I fewsn wJ Wo7-Discoux6c.769 nx0 r-MC60 - / Asest m A'SSidatxC nim Tb Otstop sci ut/2i"C Mcs n ? Number of Concerns: 1 j Eeployee Receiving Allegation: j (first two initials and last name) l Type of Regulated Activity (a) 2 Reactor (d _ Safeguards j (b) _ Vendor (e _ Other: (c) _ Materials (Specify) i Materials License No. (if applicable): i j functionalArea(s): A(a) Operations (e) Energency Preparedness / (b) Construction (f) Onsite Health and Safety i (c) Safeguards (g) Offsite Health and Safety (d) Transportation (h)Other: 4 1 ~. '. ' '.... ~ - . - -" :. -- ; n r& : (NRC Regfon I form 207 % -.' s 2, -i.:. f.';..i r c f..- a Revised 30/59); 'Y ' 0 ./;..lF,.@s.' JW.F. :.};. a' i " ".. .,. f.;c N :.'.intemiation"in this icutd dsM. efs j tm mir,El...:;g-ikgff j k[%g m act.cidance mth the~ :retco.; $ - . x Q }ff 1r.fc.. l>[. .. a e :..... 3 ;.".'...... ;.~,-j.... t,. ' j ~ ~ rom. fL=/fe t :.. ~ ~ [-.
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