ML20236S628
| ML20236S628 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 11/08/1983 |
| From: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | AFFILIATION NOT ASSIGNED |
| Shared Package | |
| ML20236S530 | List: |
| References | |
| FOIA-84-743 NUDOCS 8711300009 | |
| Download: ML20236S628 (5) | |
Text
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- k NUCLEAR REEULATORY COMMISSION
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- 3 f 1450 MARIA LANE, sulTE 210 WALNUT CREEK, CALIFORNIA 94596 ....w I NOV 8 1983 [ ~ L,
Subject:
Allegation File Number RV-83-A-0052 Dear This refers to your November 4, 1983 telephone call wherein you discussed certain welding related concerns at Diablo Canyon Unit 1 with Messrs. D. F. Kirsch and O. C. Shackleton of this office. The purpose of this letter is to inform you of our understanding of your concerns thus affording you the-opportunity to correct any misconceptions. An enclosure to this letter documents your concerns as I. understand them based on our conversation. I have requested that our inspectors look into this matter during their next upcoming inspection, therefore, if the enclosure does not completely and accurately reflect the concerns you identified, please contact me collect as soon as possible at (415) 943-3700. If you should call and I'am not available, please leave a message so that I can return your call. l .Regarding your request for confidentiality, let me assure you that'we will j make every attempt to handle this matter in such a way as to maintain your' anonymity. In this respect, I would like to point out that licensees sometimes correctly guess the identity.of the individual providing information to us. In such cases our policy is to neither confins or deny the accuracy of their guess. In closing, we appreciate your bringing your concerns to our attention. If you have additional information, or if I can be of further assistance in this niatter, please do not hesitate to contact me. 3 Sincerely, D. F. Kirsch, Chief Reactor Projects Section 3
Enclosure:
Statement of Concerns e 9 9 q
i Stateeznt of Cencarns At about 3:45 p.m. PDT on November 4, 1983, 1sstated the statedthattheinformationwasthirdorfourthhandandbasedu[poncasual ) following cencern to Messrs. D. F. Kirsch an O. C. Shackleton. conversation with the i for the H. P. Foley Company at Diablo Canyon. A weld inspector, employed by under contract to H. P. Foley Company, has evidently stated to .that-i defective weld reports prepared by-him were being rejected by the H. P. Foley Company. The. and inspector evidently felt that the rejected defective i [ldreg)ortsreportedvalidwelddefects. we The inspector's last name is l (first name unknown). t 6 4D e 6 1 4 9 m se
m,. t Pacific G2s n=d Electric Ccapeny P an gf ' 77 Bacle Street, Rcom 1435 MWr 1 h San Francisco, Californi's 94106 tQo So-2"Itb/B'JW Attention: Mr. J. O. Schuyler,f Vice President FM dm ume^ *b ' Nuclear Power Generation -o f a.tle g e hb RV Acos 2. , Gentlemen: This refers t.o the routine, monthly inspection conducted by Mr. M. M. Mendonca of this office during the period of October 30 through 3/g6 November 26, 1983, of activities authorized by NRC License No. DPR-76, and to the discussions of our findings held with Mr. Thornberry and other members of your staff at the conclusion of this inspection. Areas examined during this inspection are described in the enclosed inspection report. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations by the inspector. During this inspection period a large amount of water from the condensate storage tank was inadvertently spilled into the auxiliary building drain system. As described in the enclosed report, this event may have been somewhat mitigated with better communications within your organization. As you know, effective communications within your organization at all levels is essential to the transition from construction through startup and into operations. Your continuing efforts in this area will be closely followed ir. car inspection program. No items of noncompliance with NRC requirements were identiffed within the j scope of this inspection. ] In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure 4 will be placed in the NRC Public Document Room unless you notify this office, by. telephone, within ten days of the date of this letter and submit written application to withhold information contained herein within thirty days of the date of this letter. Such application must be consistent with the requirements of 2.790(b)(1). ~ 9 p( mn u is's w' a'* 0 , nnn ~ [ _..~ . x ~m __________A
Pac 1fic Gas cod Electric Company 2 Ut.U13NJT ~' Should you have any questions about this inspectfon, we will be g,ad to l discuss them with you. Sincerely, tu..,it.:,t t.y..::' Ey D. F., R'uli T. W. Bishop, Director Division of Reactor Safety and Projects
Enclosure:
NRC Inspection Report No. 50-275/83-36 cc w/o enclosure: J. D. Shiffer, PGE S. D. Skidmore, PGE P. A. Crane, Jr., PGE cc w/ enclosure: R. C. Thornberry,. PGE (Diablo Canyon) bec: RSB/ Document Control Desk (RIDS) Distributed by RV: State of CA (Johnson) Resident Inspector Martin RV/jk MO ONCA KI CH BISHOP 4 12/ /83 12 /83 12//J /83 D g. j l" 9 + =, ', p " ' e. $ ,a U-y s.' ~ ' ' _ _ ,:. i 'y '. ~- *- . l Aj Y. j f,
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].. Wurvainife.nca . The inspector observed portions of the surveillance test P-2B conducted cn centrifugal charging pump 1-2. The test demonstrates pump operability by the establishment of recirculation flow and the observation of bearing vibrations, lube oil temperature, and motor current. The test verified pump operability for a boration path. The inspector also observed portions of the control rod assembly drag testing. This testing was conducted per maintenance procedure M-7.13. It consisted of using the control rod latching tool with a._ scale to lift and lower latched control rod assemblies (control rod and drive shaft). The force required to accomplish this was monitored to assure the rod assemblies moved within limits. Two of the rod assemblies did not satisfy the acceptance criteria. Examination of these assemblies showed that one of the rodlets in each assembly was bowed. This interference has been identified as the cause of the failure to pass the drag test. The assemblies that failed the drag test were, therefore, replaced and the replacement assemblies did pass the drag test. No items of noncompliance or deviations were identified. 6. Allegation Followup a. Unacceptable Work and Corrective Action An allegaticu was made through a concerned citizen that an individual that worked at the plant had knowledge of unacceptable work and cor.rective actions regarding Foley welding activities (Allegation No. RV-83-A00052). Three separate interviews were conducted with the individual referred to by the concerned citizen (hereinafter the individual will be referred to as the interviewee). The interviewee was infonned that a citizen had heard that: (1) resolutions of inspection reports, identifying unacceptable work, were inadequate in the' interviewee's opinion, and (2) general Foley welding work practices were not in compliance with codes, standards or good work principles. The interviewee was asked if he had any knowledge of such problems. The interviewee was also informed of his responsibility to the regulations to identify any perceived safety concerns and that anonymity would be maintained. The interviewee expressed surprise that such an allegation had been made. The interviewee stated that he knew of no items in noncompliance with codes and standards which had not been identified and resolved. However, the interviewee felt that while work practices in some areas could be performed in a more efficient manner, they were not in noncompliance with NRC regulations or with licensee or contractor procedures. No items of noncompliance or deviations were identified. ~ O e 4 .5 M a. n., I q r., .,1. *'
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" f ".. I j ~ ~ ~ ~ REGION V 8 o, 1450 MARIA LANE, SulTE 210 ,g. ,/- WALNUT CREEK, CALIFORNIA 94596 t Y Docket No. 50-275 N b5P" sc,_ e s./ s a,-
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0, Mbu k ah M l ~ Pacific Gas and Electric Coit ay 4 b'N b# 77 Beale Street, Room 1435 San Francisco, California 94106 _f Attention: Mr. J. O. Schuyler, Vice President @/B' Nuclear Power Generation Gentlemen: This refers to the routine, monthly inspection conducted by Messrs. M. M. Mendonca and M. L. Padovan of this office during,the period of November 27, through December 31, 1983, of activities authoriz'ed by NRC License No. DPR-76, and to the. discussions of our findings held with Mr. Thornberry and other members of your staff at the conclusion of this inspection. Areas examined during the inspection are described in the enclosed inspection report. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations by the inspectors. Based on the results of this inspection, it appears that two of your activities were not conducted in full compliance with NRC requirements, as set forth in the Notice of Violation, enclosed herewith as Appendix A. Most of these violations and other events and conditions, as described in paragraph 2 of the enclosed inspection report, have been considered in a special Plant Staff Review Committee (PSRC) meeting and in a meeting between Messrs. Shiffer and Thornberry of your staff and the resident inspectors. The PSRC meeting centered on operational errors, corrective actions, and, most importantly, underlying causes. The meeting with Messrs. Shiffer and Thornberry centered on the management control aspects for problem assessment and resolution. In this meeting, the discussion lead the inspectors to conclude that schedule pressures may be attributing to the observed errors. This conclusion has been further confirmed by the resident inspectors in discussions with membeers of the plant staff. Specifically, the hurried atmosphere of work activities, with extensive use of overtime, can result in less effective work as demonstrated by the previously mentioned operational errors. From these meetings, and your staff's discussions with the resident inspectors on these topics, we understand that you and your management are aware of this management control problem and should be taking actions to address the problems. These corrective actions should be discussed in your response to the Notice of Violation. t I
Paiific Gas and Electric Company, Your response to this notice is to be submitted in accordance with the provisions of 10 CFR 2.201 as stated in Appendix A, Notice of Violation. In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure will be placed in the NRC Public Document Room unless you notify this office, by telephone, within ten days of the date of this letter and submit written ' application to withhold information contained herein within thirty days of the date of this letter. Such application must be consistent with the requirements of 2.790(b)(1). Should you have any questions concerning this inspection, we will be glad to discuss them with you. The responses directed by this letter, and the accompanying Notice, are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96-511. Sincerely, T. W. Bishop, Director Division of Reactor Safety and Projects
Enclosures:
1. Appendix A, Notice of Violation In'pection Report 2. s No.'50-275/83-41 cc w/o enclosure: J. D. Shiffer, PG&E S. D. Skidmore, PG&E P..A. Crane, Jr., PG&E Sandra Silver cc w/ enclosure: R. C. Thornberry, PG&E (Diablo Canyon) e e
. operster. The shop work followar associated with the work identified that the installed temporery hsndle was to be removed. No items of noncompliance or deviations were identified. 7. LER Follow-up l LER 81-03 involved replacement of cable connectors with more flexible devices. This work has been completed in accordance with the licensees onsite QA program and has been previously discussed with the plant engineer for adequate technical resolution. This acceptably closes LER 81-03. ~ LER 83-22 reported a condition where the raw water reservoir was separated from the fire suppression system. This condition arose because of isolation of a break that was caused when General Construction personnel attempted to open the already open valve in response to a fire alarm. The construction personnel did not know the valve had already been opened by operations personnel but they did know that they are normally not to operate such plant equipment. They responded to an emergency condition as best they could. The raw water reservoir was promptly returned to service for the fire suppression system after the The response and resolution to this event closes LER 83-22. event. No items of noncompliance or deviations were identified. 8. Potential Generic Issue Regarding Spurious Safety Injections (SI) at Low Temperature and Pressur_e Open item 83-19-04 followed a concern that was the subject of an NRC internal memorandum. This topic was also the subject of an IEE Notice 83-30. The licensee's response to this notice followed the Westinghouse Owners Group Emergency Response Guidelines (WOGERGs). The WOGERGs required that for an inadvertent SI at low temperature and pressure conditions, the operator can terminate the SI and restore normal charging and letdown once a stable pressure and other conditions for adequate core cooling. This will prevent potential steam generator pressure differentials across tubes beyond the 1600 psi design limit and thereby prevent PORV lifts that could have occurred within the previous guideline to establish RCS pressure at 2000 psi. This closes open item 83-19-04. No items of noncompliance or deviations were identified. 9. Allegation Follow-up Allegation number RV-83-A-0052 reported that an individual at the site had knowledge of unacceptable work activities and associated corrective action. Specifically, problem reports that were prepared by this individual were felt not to be adequately addressed using the in place corrective action system. The alleger had been interviewed and had no such concerns (see inspection report number 50-275/83-36). d.9%h u.4M %MCh l 4 aswMy y wm 1
e 6 ~ A3. fc11cw-up, ca inapacter c::tceted the alleger again and requested specific identification of the in question problem reports. The alleger had prepared eleven such reports and the inspectors found that ten of the reports had completed corrective actions. The inspectors reviewed these ten documents, and found that these problem reports were. acceptably addressed and resolved. That is, the corrective actions included acceptable engineering review, and where required. physical or procedural modifications. .This closes this allegation, because the gleventh item was not significant. i i No items of noncompliance or deviations. were identified. 10. Steam Generator Snubbers Each steam generator has four hydraulic snubbers which utilize "Buna - N" seals and are connected to a common reservoir containing GE or Parker SF-1154 silicone base hydraulic oil. j Paul Monroe, the snubber manufacturer, has indicated that the seal material is not compatible with the hydraulic fluid, and that the seals should be replacea every five years. The steam generator snubber seals at Diablo Canyon are about 12 years old. Visual inspection of these snubbers and discussions with PG&E plant personnel, indicate that in most plants seal replacement is based upon seal leakage, only. PG&E is considering replacing the seals on the Unit 2 steam generator snubbers with a "Tefzel" seal material which is expected to last 40 year?. Similarly, PG&E is also considering replacing-the seals on Unit 1 at the first refueling outage. Consideration is also i being given to installation of a level indication system on the hydraulic reservoirs to detect seal leakage. Follow-up of the licensee's co' rrective actions on this subject will be performed under normal inspection activities. No items of noncompliance or deviations were identified. 11. Residual Heat Removal (RHR) System Snubbers \\ Snubbers on the RHR system, which were determined by the licensee to be inoperable, were examined. Hanger No. 15/94SI (consisting of a support and a PSA-3 snubber) on the RHR pump 1-1 and 1-2 suction from the Refueling Water Storage Tank was declared inoperable, because four capscrews connecting the snubber to the RHR pipe support were too short for correct thread engagement. The corrective action consisted of replacing the short capscrews with capscrews of adequate length. t. Other snubbers were found by PG&E to have spherical bearings out of place due to inadequate staking of the bearings. these snubbers were returned to service. After completion of repairs, t 1 I No items of noncompliance or deviations were identified. 12. Exit Meeting O
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- 1. Facl!!ty(Iss) Invclved:
IN.b11M].)) & po,c/ - l 0 f 0 o e 3 7 f l 1 In no.. e ns. - n gen.nc, wm. GENEAlC) ] I l ~
- 2. Functional Areals) Involved:
onsite health and safety l tch.ci.ppropriate boalmil operations construction offsite health and safety safeguards emergency preparedness ~ other tsp.estyl 3.
Description:
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- 4. Source of Allegat. ion:
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- 5. Date A!!egation Received:
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- 6. Name of Individual tre. two i it.
.n .. n.m.) Receiving Allegation: / ' 7. Of ficei 2 ll ACTION OFFICE d [> /
- 8. Action Office
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- 9. FTS Telephone Number:
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- 10. Status:
Open, if followup actions are pending or in progress (Check on.) Closed,if followup actions are completed MM DD W ~ C) C 11.1 Doctament Hos. ErkWCN
- 11. Date Closed:
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l~. t Rb gy - A,g[M [ 76' Propescd Inspretien Plan l. Region V action j l a. Examine H. P. Foley records of National Inspection and Consulting J Company personnel at Diablo Canyon under contract to perform inspections. b. Determine (1) Full name (2) Address in the local area (3) Telephone number ] c. Arrange to interview s soon as possible. d. Interview' }(Documden .r.nterview on Inteli'iew Sheet) i aay ~ea.sm r rs.
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Area where he is assigned to perform inspections. 1 I (2) What items did he issue defective weld reports on. Obtain as many specifics as possible including copies of the rejected defective weld reports if possible? (3) Who in H. P. Foley is mainly responsible for rejecting these reports? q (4) What kinds of discrepancies were documented on the defective weld reports? ($) boss Ne fnGL TMT ARIY Of kt3 A.#Wp 998 de1* BZ2A PR.oNDY AhloLWO $ Examine items identified by [ ing and code requirements. Jin the field to ascertain the e. degree of compliance with draw f. Document findings in an inspection report and issue. r g. Close out issue by providingi with a copy of the inspection reportT h. Close out ATS-83-A-0052. 1 2. The Allegation Review Board met on and approved the above course of action. i l Review board members were: 1 . W. Bishop Chairman A. D. Johnson Allegation Tracking System Coordinator D. F. Kirsch Section Chief I J. L. Crews 1 I N._--N- -}}