ML20206C425
| ML20206C425 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/06/1987 |
| From: | Brown W, Carey P, Stewart D TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20206C172 | List: |
| References | |
| 80303-SQN, 80303-SQN-R04, 80303-SQN-R4, NUDOCS 8704130052 | |
| Download: ML20206C425 (40) | |
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g J " ,, TVA EMPLOYEE CONCERNS REPORT NUMBER:
, .'. REPORT TYPE SPECIAL PROGRAM 80303-SQN Element Report REVISION NUMBER:
TITLE: 4 QA Personnel - Personnel-Training and Experience PAGE 1 0F 14 REASON FOR REVISION: Incorporation of Corrective Action responses. Revision indicators are noted in right margins >n pages as needed. Note: Sequoyah Applicability Only PREPARATION PREPARED BY: P. Carey 0 08 SIGNATURE / s/es/P7 DATE REVIEWS PEER: C64L A7/87 DATE' [/' SIONfTURE TAS: f/ f DATE SIGNATURE CONCURRENCES CEG-H : n!87 SRP : M k NW Y- 3 ~87 DATE SIGNATURE DATE GNATURE* APPROVED : J W] fn f N/A MANAGER OF NUCLEAR DATE ECSP 'MAIIAGER (j D$E [ l POWER CONCURRENCE (FINAL REPORT ONLY)
*SRP Secretary's signature denotes SRP concurrences are in files.
8704130052 870406 PDR ADOCK 05000327 P pop
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' REPORT NUMBER:
, [- 80303-SQN REPORT TYPE: REVISION NUMBER:
Element Report 4 TITLE: 'PAGE 2 OF 14 i Personnel-Training and Experience. 4 1.0 CHARACTERIZATION OF ISSUE 1.1 Introduction-The issues described in this Element Report was derived from employee 7 concerns generated ~ as a result of ' the Watts Bar Employee Concern Special Program (ECSP). These concerns were determined to be applicable to the Sequoyah Nucicar (SQN) Plant and were . investigated and evaluated on that basis. Two of the concerns were determined to be Sequoyah specific, the other concern was generically applicable. 1.2 Description of Issues 4 The issues reported by concerned employees (Attachment A), and _ as noted below, were grouped by issue under this element -- Personnel-Training'and Experience. A. SQN procedure for handling safety concerns not being followed. i Concerned Individual (CI) did not receive written feedback pertaining to a condition reported by the CI on a TVA form 45. (I-86-211-SQN, dated January 30, 1986) B. Training and experience of selected Quality Assurance- (QA)
' personnel. (SQM-86-009-008, dated February 12, 1986)
NOTE: Employee concern as described in Attachment A also addressed Management lying to the Power Operations i Training Center (POTC) with regard to training and i. experience of selected QA personnel, however, that portion '- of the concern is addressed by the Management and i Personnel Category Evaluation Group. e C. Engineers in the Electrical Design Branch are not being trained in the preparation of electrical calculations. This is a multi-part concern which is assigned to the Engineering Evaluation > Group. However, the Quality Assurance Category Evaluation Group (QACEG) has been assigned to evaluate the training portion of
- that concern. (I-85-128-NPS, dated February 18, 1986)
D. Welder Continuity Program at SQN does not ensure that welder's 4 l maintain proficiency. (JLH-85-001, dated August 26, 1985) i 2.0
SUMMARY
t I '2.1 Summary of Characterization of Issues The issues disclosed by concerned employees are: SQN procedure for handling safety concerns not being followed in relation to feedback to the Concerned Individual (CI), inadequate training and experience of h
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c:J REPORT TYPE: 80303-SQN c.: Element Report REVISION NUMBER: TITLE: 4 Personnel-Training and Experience PAGE 3 0F 14 selected - QA personnel by POTC, electrical engineers are not being trained in the preparation of electrical calculations, and the welder 4 continuity program at SQN does not ensure that welders maintain proficiency. 2.2 Summary of Evaluation Process The . Quality Assurance Category Evaluation Group (QACEG) evaluation consisted of reviewing applicable procedures, audit reports, correspondence, and training records. Discussions were held with cognizant personnel to gain further facts and insight to each issue. 2.3 Summary of Findings The conclusions ' reached as a result of the QACEG evaluation of these issues are: The issue of "SQli procedure handling . safety concerns not being followed," could not be verified as substantiated or unsubstantiated since reference to the original concern information (TVA form 45) was unobtainable. The issue of " Management lying to the POTC," was addressed in a report issued by the Division of Quality Assurance (DQA) and will not be evaluated by QACEG. The DQA evaluation determined that the concern was a management issue. However, the issue of experience and training by POTC of selected QA personnel was evaluated by QACEG utilizing Nuclear Safety' Review Staff (NSRS) reports, QA audit reports, and the evaluation conducted by Division of Quality Assurance as documented in their report. This issue was found to be unsubstantiated, however 4 ! there were many problems noted in the implementation of the certification program. The issue of " Electrical Design Branch Engineers not being 1 trained in the preparation of calculations," was found to be i unsubstantiated. However, the QACEG investigation indicated training had not been accomplished to the latest issue of Nuclear Engineering Procedures (NEP) NEP-3.1, Revision 0, dated July 1, j 1986 and NEP 9.1, Revision 0, dated July 1,1986. f The issue of the welder continuity program at SQN not ensuring that welder's maintain proficiency is unsubstantiated. 4 ( o 2.4 Corrective Actions Taken And The Results Achieved To Date 2.4.1 Issue - " Training and experience of selected QA personnel." i
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- REPORT NUMBER:
** 80303-SQN
'- REPORT TYPE: .
REVISION NUMBER:
. Element Report 4
TITLE: PAGE 4 OF 14 Personnel-Training and Experience I i Deficiencies with the implementation of program requirements 4 as noted in SQN Corrective Action Request (CAR) 86-01-003 were verified as corrected and closed through a ' follow up surveillance.
- Four of the six recommendations issued by NSRS were closed either af ter the investigation, or determined that no action was required, or action was required and scheduled to be a date. The remaining two implemented at later recommendations from NSRS were reviewed and evaluated by the Division of Quality Assurance for validity of the concern.
Any deficiencies that were' identified during the. investigation. were corrected. 2.4.2 Issue - " Electrical Design Branch Engineers are not being trained in the preparation of electrical calculations." The training records for the engineers assigned to' the Sequoyah Project. Office at Knoxville indicated they were trained to the requirements of NEP 3.1, " Calculations" and NEP 9.1, " Corrective Action" which pertains to the revision of calculations. 3.0 LIST OF EVALUATORS P. A. Carey W. E. Bezanson 4.0 EVALUATION PROCESS 4.1 General Methods of Evaluation , The evaluation process consisted of reviewing procedures relating to documentation, the issues, applicable audit reports, training Division of . Quality correspondence, NSRS investigation reports, Assurance investigation reports, and outside contractor assessment reports to determine the requirements, extent of the issues, and corrective actions taken. Discussions were held with responsible personnel pertaining to the issues described within this Element Report. 4.2 Specifics of Evaluation 4.2.1 Issue- SQN Procedure for handling safety concerns not being followed.
- REPORT NUMBER f ( ** r REPORT TYPE: 80303-SQN Element Report ,
REVISION NUMBER: TITLE:- 4 Personnel-Training and Experience PAGE 5 OF 14 QACEG's evaluation process consisted of reviewing procedures pertaining to the Employee Concern Program at Sequoyah. These procedures are as follows: Nuclear' Safety Review Staff Office Procedures 0207 " Handling Employee Concerns", Revision 1, dated July 25, 1985 0307 " Employee Response Team Program", Revision 3, dated November 6, 1985. 0308 " Employee Response Team Program Administration", Revision 2, dated September 16, 1985. Sequoyah Standard Practice SQA 178 "TVA Of fice of Nuclear Power Employee Concern Program Line Organization- Procedure", Revision 0, dated February 6, 1986. The above procedures pertained to past methods used for-conducting investigations of employee concerns at Sequoyah. QACEG reviewed NSRS Report I-85-135-SQN, dated February 18, 1986, documenting an investigation of another concern which identified the same issue as described in Concern SQM-6-009-008. Discussions were held with a former NSRS investigator to obtain additional information pertaining to the notification of the NSRS evaluation results. 4.2.2 Issue- Training and experience of selected QA personnel. QACEG evaluation process consisted of reviewing NSRS Report I-86-109-SQN pertaining to this issue. The evaluation process encompassed investigating and verifying two areas of concern: (a) formal training was provided by POTC for QC inspectors as required; and (b) experience obtained through on-the-job instruction and performance that satisfies minimal experience requirements prior to certification. In addition, based on two recommendations made by NSRS, QACEG reviewed an evaluation report issued by the Division of Quality Assurance addressing the validity of this concern. QACEG and NSRS evaluations included reviews of procedures, instructions, and various documents such as certification records at POTC, and SQN Site Quality Control (QC) Files, QC Daily Work Logs, personnel history records, QC Inspector Training Manuals and On-The-Job Training Manuals. These
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- - REPORT NUMBER:
80303-SQN
. - . REPORT TYPE:
glement Report REVISION NUMBER: TITLE: 4 Personnel-Training and Experience PAGE 6 0F 14 documents were reviewed as they identified the requirements and commitments for the issue. In addition, discussions were held with POTC personnel, QC management personnel and QC inspection personnel ~ pertaining to this issue. 4.2.3 Issue- Engineers 'in the Electrical Design Branch are not trained in the preparation of calculations. QACEG . evaluation process consisted of reviewing applicable; < procedures pertaining to the Electrical Design Branch Training at Sequoyah. Those documents were reviewed as they reflected - the programs in effect when the concern was addressed: Office of Engineering Procedures (OEP) OEP-06, " Design Input", Revision 0, dated April 26, 1985 OEP-08, " Design Outputs", Revision 0, dated April 26, 1985 OEP-18, " Training", Revision 0, dated July 1, 1985 OEP-07, " Calculations", Revision 0, dated April 26, 1985 Nuclear Engineering Procedure (NEP) NEP-1.2, " Training", Revision 0, dated July 1, 1986 NEP-3.1, " Calculations", Revision 0, dated July 1,1986 NEP-9.1, " Corrective Action", Revision 0, dated July 1, 1986 NEP-6.1, " Change Control", Revision 0, dated July 1,1986 The OEPs were changed to NEPs to reflect new organizational changes .within TVA. QACEG's review of the procedures l indicated they were basically the same, with the new procedures reflecting only minor editorial and organization title changes. The following Engineering Assurance (EA) audit reports were reviewed, as they addressed the above calculation and training l procedures: Audits EA-86-17, dated March 10-17, 1986 Sequoyah ! EA-86-23, dated August 4-8, 1986 Sequoyah l- TVA Division of Engineering Design } l EEB-EP 22.31 - Electrical Engineering Branch Training Procedure, Revision 0, dated March 7, 1986 i i Training records were obtained for personnel in the Electrical Engineering Branch in Knoxville and Sequoyah. These were l l t
. .. ' , REPORT NUMBER A .' REPORT TYPE:l 80303-SQN
-Element Report- REVISION NUMBER:
TITLE: 4 Personnel-Training and Experience PAGE 7 OF 14 reviewed to determine what training was conducted during the s period of 1985 to 1986. Discussions were held with the Assistant Electrical Branch Chief within the . Electrical' Engineering Branch in Knoxville and the Lead Electrical Branch Chief at . Sequoyah to determine the 'easoning r behind the deficiencies in the Electrical Design
- Calculation Program, as' identified in the EA Audit Reports.
4.2.4 Issue -- Welder continuity program at SQN does not ensure that welder's maintain proficiency. 4 QACEG evaluation process consisted of reviewing the " Welding Performance Qualification Continuity" -Report WP-03-SQN,
- Revision 2 issued by the Welding Project.
5.0 FINDINGS 5.1 Issue- 'SQN Procedure for handling safety concerns not being followed. 5.1.1 Discussion Research -for this concern revealed that NSRS performed an investigation (Report 1-85-135-SQN, performed November 26 through December 12, 1985) of the Walder Certification Update Program as a result of Concern Numbers XX-85-049-001 and XX-85-049-X03. The issue derived from those two concerns is the same issue identified in Concern Number I-86-211-SQN and described in this Element Report. The results of the NSRS investigation (per NSRS Report I 135-SQN) were forwarded to Quality Technology Company (QTC) on February 18, 1986, at Watts Bar (via carbon copy and
- l. attachment of letter to H.L. Abercrombie, Site Director, SQN,
- from K.W. Whitt, Director of NSRS). It was not NSRS's i practice to respond directly to the Concerned Individual (CI)
( beyond September, 1985. Their reports were distributed to QTC and it was QTC's responsibility to submit results of the l investigation to the CI. ! 5.1.2 conclusion i ) Since QTC records are unavailable for QACEG review, a. l determination of whether Concern I-86-211-SQN was i substantiated or unsubstantiated cannot be determined since a l reference to the original concern number was unobtainable. As the specific issue addressed within Concern I-86-211-SQN, was with feedback to the concerned individual, QACEG does not 1
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REPORT' NUMBER
*. - REPORT TYPE: 80303-SQN Element. Report -REVISION NUMBER TITLE:- .
4 { Personnel-Training and Experience' PACE 8 0F 14 t 4 . consider ' this to be a problem that would potentially impact safety. !, 5.2 Issue- Training and experience of selected QA personnel. 5.2.1 Discussion NSRS Report I-86-109-SQN documented inconsistencies within the certification files at POTC and the QC certification files at SQN. In particular, a lack of documentation supporting waiver of previous experience, certification, and inconsistent ' on-
- the-job training (0JT) documentation. Previously, a SQN
; Inplant Survey Checklist No. 2-28-S-001, performed January 25-28, 1986, reflected several related deficiencies that were i later documented on CAR 86-01-003, issued January 31, 1986, by j QA. CAR- 86-01-003 documents expired certifications and inadequacies in the continuity of certification documentation. -
SQN Master List of NDE certified inspectors reflects t inaccurate certification expiration dates and eye examination , i due - dates. Eye examinations had expired and some inspectors were still performing inspections. Certification forms were not properly completed in some instances, and previous < experience waivers were not signed by the Field Quality- , I Engineering (QE) Staff Chief. I An approved' corrective action plan was submitted to R. B. Kelly, Director of Nuclear Quality Assurance, providing- a summary of corrective action status on June 1, 1986. It was , j 'noted all corrective actions were complete for CAR 86-01-003, with the exception of response to NSRS Report I-85-373-NPS. Response to I-86-373-NPS was subsequently submitted July 29, i 1986. Verification of corrective action was conducted through j Inplant Survey 21-86-S-026,~ conducted July 30-31, 1986. i As a result of NSRS's evaluation and recommendations, a detailed review was performed by the Division of Nuclear l Quality Assurance, in August 1986, to verify 1he validity of i training and experience of selected QC personnel at SQN. 1 Specifically, the Division of Quality Assurance addressed recommendations I-86-109-SQN-02 and -04. (Recommendations I-i 86-109-SQN-01, -03, -05, and -06 had been previously closed i out by responsible organizations) Letters from C. C. Mason to R. K. Seiberling, dated May 23, 1986, and from H. L. Abercrombie to R. K. Seiberling (no date) document closures. i
- The DQA review was conducted to determine the following, with regard to QC Certification Files of inspectors presently at SQN
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. REPORT NUMBERt -
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. . - ' REPORT TYPE:~ 80303-SQN glement Report ' REVISION NUMBER:
TITLE: . 4
' Personnel-Training and Experience PAGE 9.0F 14
- a. Determine if the -program described in NQAM, Part II, Section 5.3A was met.
- b. Establish on-the-job training (0JT) ' practices that .were used .to certify individuals in areas where - little or no opportunity for OJT existed.
- c. Determine if the OJT time period was waived on initial certifications. In these cases, supporting documentation will be obtained and included in the certification files at the site.
The results of these reports indicated that QC ins pectors , whose certifications had' expired due to lack of documentation of experience or training, were in fact properly trained, had necessary experience, and were certified. The DQA review
. indicated that inspectors had either adequate OJT or adequate backup documentation for experience waivers prior to certification. In each case, it was determined that certification problems were of an administrative nature and no i re-inspections were. required. Inspectors whose eye certifications had expired were retested. All but one inspector passed the retest. In the one case, a sample of individuals work was reinspected and found to be acceptable.
5.2.2 Conclusion The issue of training and experience by POTC of selected QA personnel is unsubstantiatwd based on the findings identified in previous NSRS reports, the Division of Quality Assurance report, and this Element Report. However, improvements in the training and certification program of QA personnel was , required and is presently underway on an interim basis per i Nuclear Quality Assurance Manual (NQAM) Part II, Section 5.3A. l Unti1~ the New Quality Control Inspector Training Program is ! j- developed and proceduralized by the Technical Support Branch j in Chattanooga, CATD 80303-SQN-01 was issued to incorporate a i tracking method to ensure that this new training program becomes implemented and evaluated as effective. t 5.3 Issue- Engineers in the Electrical Design Branch are not trained in l the preparation of electrical calculations. i l 5.3.1 Discussion l Procedures were reviewed as referenced in Section 4.2 of this Element Report. It was determined that procedures for preparation and control of calculations were in place, however, engineers were not complying with the procedures. This is evident based on the results of the Engineering Assurance audits described within this element report.
+.. i ' REPORT NUMBER:-
*1* 80303-SQN
' REPORT TYPE:
Element Report REVISION NUMBER: TITLE: 4
-Personnel-Training and Experience PAGE 10 0F 14 Audit Report EA-86-17 conducted in March 1986 cited eight-deficiencies, four pertaining to calculations. Calculations were not retrievable, -independent reviews of calculations were not performed, calculations were not prepared in accordance with procedures, calculation logs were not up to date, drawings issued prior to issuance of related calculations, and training records were not complete. The report also stated all training had'been conducted,- but documentation had not been submitted to the Electrical Engineering Branch - Document Control Section. All of the deficiencies cited' pertaining to calculations and training of engineering personnel remain open as of this' investigation.
Audit Report EA-86-23 conducted in August, 1986 cited eight deficiencies pertaining .to preparation and control 'of electrical calculations; calculation logs not being maintained, drawings do not reference applicable calculations, and no documented evidence of training to applicable procedures was available. This report - also stated that the TVA employees had been trained to the OEPs which were in effect during 1985. Three of the deficiencies pertaining- to calculations remain open as of this investigation. Those open deficiencies identified in the above reports will not be addressed in ~ this report, as they will be resolved by the EA Audit Program. Training records that were obtained from the Electrical Design Branch for .the Sequoyah Project in Knoxville and the Sequoyah site were reviewed as per requirements of EEB-EP 22.31, Revision 0, dated March 7, 1986. Personnel were trained to Office of Engineering Procedures (OEP) 06, " Design Input", OEP-08, " Design Output", and OEP-07, " Calculation", and tested in all three procedures under training session QA 103 during 1985 and 1986 as verified by training attendance sheets. Subsequent to the OEP training, the Office of Engineering , Procedures were revised under the new organization of " Nuclear l Engineering". The engineers were now required to be trained i to the' requirements of NEP 1.2, " Training", Revision 0, dated ( July 1, 1986, NEP 3.1, " Calculations", Revision 0, dated ! July 1, 1986 and NEP 9.1 " Corrective Action", Revision 0, !- dated July 1, 1986 as it pertains to the revision of calculations. As a result of these revised procedures, the training is required to be documented as per the requirements of NEP 1.2. Based on the QACEG investigation it was established, that as of October 27, 1986, the personnel in the Electrical Design Branch for Sequoyah, located in Knoxville had been trained in the requirements of NEP 3.1 and NEP 9.1. i t
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**-C iREPORT TYPE: 80303-SQN Element-Report REVISION NUMBER:-
TITLE:.. 4 , Personnel-Training and Experience PAGE 11 OF 14'
' The -QACEG's review of training record for Electrical Design
' Branch Engineers , located at Sequoyah, indicated they had not l been trained in the requirements of NEP 3.1 and NEP 9.1. This was due to the priority of the system walkdown effort being performed at SQN. As a result, CATD 80303-SQN-02 is being issued - to ensure that Electrical. Design Branch Engineers at SQN, will be trained to the NEP 3.1 and NEP 9.1 requirements.
Through discussions between this evaluator and the Assistant Electrical Branch Chief, 'in the Electrical Engineering Branch in' Knoxville, and evaluation of those documents described-within this element report, indications are that the engineers were trained. However, the results of the EA audits indicate the training was inadequate.
-An independent assessnent was conducted by Sargent and Lundy of TVA's Electrical Calculation Program, and the results.
indicated that this program was deficient. As a result of the assessment by Sargent and Lundy, corrective ~ action is - being i implemented to improve the Electrical Calculation Program.
. A separate effort is being conducted by the Engineering Concern Task Group pertaining to the technical aspects of this concern.
3 Through the assistance of Sargent and - Lundy, TVA Electrical Engineers will undergo formal training utilizing new {
! procedures and technical guides currently being written by TVA
! with the assistance of Sargent and Lundy. In addition, TVA
- has contracted through Sargent and Lundy, a new computer i
database for use in the preparation of calculations. The intent is to train the Electrical Engineers in the use of this l program, along with new revised procedures and technical
- guides. This new training program is tentatively scheduled j for implementation the first quarter of 1987.
j' 5.3.2 Conclusien i j Based on QACEG's investigation and the review of all documents , referenced within this report, the issue is unsubstantiated. [ Training was performed to the OEPs which was the program in ! effect during the time period the employee concern was issued.
- However, based on the results of the audits and the fact that l some of the site Electrical Design Branch Engineers have not l been trained to to the new requirements of the NEPs, CATD No.
l 80303-SQN-03 was issued to ensure implementation of an I improved Training Program. Also, CATD No. 80303-SQN-02 is !' being issued to ensure site Electrical Design Branch Engineers L are trained to the present requirements of NEP 3.1 and NEP i 9.1. l l
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i* REPORT NUMBERt i*** . REPORT TYPE: 80303-SQN y - glement Report REVISION NUMBER:- 4 TITLE: Personnel-Training and Experience PAGE 12 OF 14 Until' the commencement of the new training program .and assurance of its implementation and effectiveness, the issue of electrical engineers preparing eTectrical calculations without adequate training is considered potentially safety significant. 5.4 Issue -- Welders continuity program at SQN does not ensure that welders maintain proficiency. 5.4.1 Discussion 4 " A Bechtel SQN Implementation Audit addressing . welder performance qualification and continuity activities was conducted -in January 1986. No areas of noncompliance were noted'in the audit. The welding project performed a review of the results of Bechtel SQN Implementation Audit and concluded that the technical requirements for both the program requirements and the implementation of those requirements were effectively met at SQN as documented in WP-03-SQN, Revision 2, " Welder Performance Qualification Continuity". 5.4.2 Conclusion The issue pertaining to welder continuity program at SQN not ensuring welders maintain proficiency is determined through review of the Welding Project Report by QACEG to be unsubstantiated. 5.5 Corrective Action 5.5.1 Issue - " Training and experience of selected Quality Assurance (QA) personnel." CATD 80303-SQN-01 was issued to track the implementation of the new QC inspector training program. The response to CATD 80303-SQN-01 was provided on January 9,1987 stated that on or about October 27, 1986 general quality control training commenced for current certified inspectors. Upon completion of the general training, basic and specific training will be conducted. Two certification programs will be maintained 4 until an appropriate number of QC inspectors have completed the new training program. The new training and certification program will be implemented when the individual QC inspectors have completed the req.uired training. An evaluation of the new QC training and certification program will be made after : appropriate number of inspectors have completed the program. l 1 _ _ _ ~ . - - - . . _ ,
4.. 1? REPORT NUMBER: REPORT TYPE: 80303-SQN Element Report REVISION NUMBER: TITLE: 4 Personnel-Training and Experience PAGE 13 0F 14 Issue - " Electrical Design Branch Engineers are not being 5.5.2 trained in the preparation of electrical calculations." At the time the concern was filed, the Electrical Engineers were trained in the OEPs pertaining to preparation and issuance of alectrical calculations during the one year of 1985. Effective _ July, 1986 the OEPs were changed to Nuclear Engineering Procedures (NEPs) reflecting the new TVA-organizacion. QACEG's review of training records for the engineers assigned to the Sequoyah Project Office at Knoxville indicated they were trained to the requirements of NEP 3.1, " Calculations" and NEP 9.1, " Corrective Action" which pertains to revision of calculations. The QACEG evaluation of training records for 4 the Electrical Design Branch Engineers located at the SQN site indicated the engineers were not trained to these EEPs. As a result, QACEG . issued ECSP . Corrective Action Tracking Document (CATD) No. 80303-SQN-02 to track the electrical engineer's training to NEP 3.1 and NEP 9.1 at Sequoyah. A response to CATD - 80303-SQN-02 was provided on February 13, 1987. The Electrical Engineers at Sequoyah have been trained in the current revision of NEP 3.1, " Calculations" and NEP 9.1, " Corrective Action". Attendance rosters for those individuals have been provided to QACEG showing evidence of training conducted November 24 and 25, 1986. This training will be incorporated into each individual's Training Record (ITR) per the requirements of NEP 1.2. l CATD 80303-SQN-03 was issued to track the development and i implementation of the new electrical calculation training
- program by Sargent and Lundy.
I I An updated response to CATD 80303-SQN-03 was provided on l February 13, 1987. The new training program will be ( implemented by Sargent and Lundy and TVA covering the preparation / issuance and control of electrical calculations. This is an ongoing effort that is scheduled for completion by December 31, 1988. The program as currently structured (NEP 1.2 and preliminary procedure Electrical Engineering Branch Controlling Instruction EEB-CI-2 " Training"), requires training in the basic procedure and all revisions. Initial training will be formal and for all revisions it will be either formal or reading assignments with question and answer sessions, as determined by the Branch Chief or Project Engineer. l
* ' REPORT NUMBERt REPORT TYPE: 80303-SQN
~ Element Report REVISION NUMBER:
4 TITLE: Personnel-Training and Experience PAGE 14 OF 14 Attachment A identified the- concerns as potentially safety-significant. 'However, QACEG evaluation concludes that only concern I-85-128-NPS is potentially 'saf ety-significant , but the concern is not considered . detrimental to the safe or reliable operation of the Sequoyah Nuclear Plant. A separate investigation has been conducted - by the Engineering Concern Group pertaining. to the integrity of the calculations ' and the results .will be documented in their report on Concern No. 1-85-128-NPS. 6.0 ATTACHMENTS A. Employee Concern . Program System (ECPS) List of ' Employee Concern ' Information. B. Corrective Action Tracking Document (CATD) No. 80303-SQN-01 C. Corrective Action Tracking Document (CATD) No. 80303-SQN-02 D. Corrective Action Tracking Document (CATD) No. 80303-SQN-03
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- 2. S:cp Work Ree::= ended: /_~ / Tes /.I./ No
- 3. CCD No. E0303-SON-01 l. . - IN.- A ;0N OA I 11/26/56 i .e... .
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- 1. !=:nediate Corre::ive A::icn Required:
. 2. S:op Work Re==_ ended: /~/ Yes /I/ No -/X/ Yes // No
- 3. CATD No. 80303-SON-02 /.. IN;;;ATION DA I 11/26/S6
- 5. F2sFoNs;3:.I OR AN;;A ;cn: Ilec:rical Enrineerire tranen a: SON
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As identi'ied in Ile=en: Reeer: 80303-5cN. Seeuovan Ile::rical Inrineers loca:ed a: Secuevan have ne: ~ocen : rained in HI? 3.1 "Calcula:: ens" and HI? 9.1 "Cerrective p:: en. HIP 1.2
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INITIATION -
- 1. l=:nedia:e Corre::ive A:: ion Required: ~
- 2. Stop Work Rece=:nended: -/E/ Yes /._/ No
- 3. CATD No'. 80303-SON-03
/~/ Yes /Z/ No
- 5. -
- i. :.SPC ..S. :.,.:. ORo.,.us. ... .n.. . .ON : 47 In !;ATION DATI 11/26/86
- .3.e::rical Iner. neerine 5:anen .
' 6. 3 R n.u. ~r u. D _e S .. w- r. ,. 0 . d. . /,,./
R H a.
- As identified in Elemen- Rescr: 80303-SON. a -
new revised ::aintne erce am is beirr ceveleved bv TVA and Sar:aen: and Lunov for :he
. .Elee:ri:El and
- =ntrolEnrinterint of ele :ricalir:nen =ticulz:iens. vitn re:AErd to cre: ara:icn reviev.
. .. cf .l a nu a-v 1987 has oten nc ed Dv Assis:an: verDal ::=mi: ment ca:e
- nrineers in i n exv t .i .ze ter
. Lead El e::rica l__
tretra=. = ele =entatien cf :nis nev :rzining - initia:icn However. One actual has ca:es der ererra: ::= ele:icn and of ::tinint
= anate en*.. ne: been es:zelisned 'v o
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e s 100 250 Armendix 3 and CEF-7 - w o..enesion et conosiion 8
, g Faiiure to identify the recuired -d d um se: of calculations and studies fe; i
all cle: rical sys:e=s in c: der :o establish :he technical adequacy of each
. and :na: :he design basis is =et. .
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. , There was no program in place to define the re:uired minimum set of
' calcula:icns and studies for the ele::rical systems in order to establish
, -3 te:hnical adecuacy and the desien basis er to revise the calcuhtions 8 en:e they were performed.
O - 5 .
. _m_ ~ . corr,=m Aavon .
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l A minimum set of electrical calculations has been de:ided .'=cn, p e:a ed, a.d is' cu~en:1y beine revie.ed by Sarge-. & !. undy f: ::- .e. . and j . we siveness. Foil: wing -his j reyies, :ne cair.0ati:ns will :e revised as re essary and a::;.ed f use. 1
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- 6 S.R
- Number and Revision W, AR PR (contmweel" ' '
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@ ScNeCueed Como*etion Date of CE Worli .> .
C Do.s tne correctm acuon oenate from a oess;9 c*tteria reovirement? h Yes ] No g R L . ,n cinerna Document humoer s * " i Encession Roowest hurroer O '$- i is en EON roowered? La.d.)3' - *86 58r** kas? u 2d h Yes i 1 If yes, :_CN number O Att =:: pr=iec. c= = =ie:to n eneeuie 5 m ] No j 0 ^t*== > >=8ecuie =< reietee a=:ivi1ier i
< O O N= i==e=: -
o u. Mi Re=* Concurrence win Reveew s.9neture and Dan
~
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, C IrEcation m-f Aoproval $89 nature anc Date (Distrioute as fecuired .
O o.n.r st/.B. S k. s e/sto g See bloCE E03
- RIMS Accusason humoer #
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' @ Csecurrence et Lessnatec Cuakty Rewemr for ARPR anc Date RIMS Accession hummer t (Distrimute as a=orconate.see otoen 20J t rir) Remar=: 1 r is SCR. is being vritten 1: respe:se to ?ctenzial Generi 'C di:1== Ivaluatich f= CAQs ra --+S52710, WW II3852ERO, and rd m E5291v.
7' '"his SCR* is s'- z:
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O See Continuation Sneet IT="I Au CE/OO Action Committe , ,
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U i- NRO Residen:Iri. pec: r - i CO Site Dedi:sted Oata Ea'se C"XiA c 1 Nss-N s ne==r:::B, Knoxville ,
. ji NSP.S s:=r.,ega . .
jj n OE Pr=je:: Manager I,,, ,, AN! (For Cece item Only) CO.OAE Site
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00Proje:: Manager I, [~ .,c, - 5 Chief, CMS . gw.3 Am,,,,n 3,,,,,, 3 ,,,,, OE Menager t L NEB CMS (f=r ASME C :: ttems) l l
- Y a#r . . l. 7
**
- ENbNEERING REPORT RIMS Accession Numoer
($v OE to, c? p ent) * -
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. 0 __ isy uu: Pm to, et Pianti ""'0"*
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<<W Io E.
*5ee Note 2 on osee 4 ter comoietene Part B . Part a coni nvec on osees ; ene 2
] Yes (CL Nuclear Planu Onsy) Out Date of Fanure Evniustion Preparation of Failure No Eveauation is recuested by NUC PR7 ,
Conciusions (See Note 2J , g . .
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. 1
- 2 Recommencations (See Note 4.)
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C;erauona! LimrtrJons/Acuans
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Jus.ifscraon For ContinueC Coerraon .
- g. Sussested Correr.ive A=uon S
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..........................................................l Y es No FSAR Revision Recuired?
........................................................................ Yes No Deficiency Adversely Affer.: Safe Coerrtion of Plant?
/_e CE Contar.
..................................................l Yes No w Accrovec Ev anc Dete Preparec By an: Oate TvA 1:::.e r g,. oes . . e.....
.. C:ET - 17 ,
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g g,,, CAC Report No, anc Rev. Pace 2 of 4 D , 1 Taculate Data on All Faisec ancier Affe:Ted Comconents. Stru=Ures. anc Syste ns: Give oesenstions. mocel an
/ rnanufa=urers namDers, ano orsginas anc reviseo cesign criterna anc/or spe:111:ations. (See Note 5.) - ]
i 1 2. Failure Me:nardsms of Atte tee Comeonenu. 5 ru=ures. anc Systems: State wnetner e2:n atie=ed component,
- ru::ure, crH., recu:ed anc system
- aca:ity,ce:ame c::. (Seeopen Noteor6.):sosec, inextative, or snorie ;or na: shortened life, reduced a :gracy,in= eased
, = D:.. .
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. - 3. . . 3...
. .T T e .
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- 2. Alter .zte Uses and Generi: imeii a.icn :
1 paar::. D:::uss geners: ampit:a: ens. (See tvcte 1:en-ity 7.) a: ternate uses of :ne : mponents, struc. ires, and systems in :ne ,
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4 Cemeener::. S: u=u e. ane/er System Kailure Mocetsh
- Give ces=iption and extent cY effe::: cf tailures on ca..
. compon.er: ::ru=ure, ancier system invoive:. (See tvc:e E.). . -
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S , Part B (Continuid) gR Rev. CAO Report No.and Rev. Page 3 of 4
.g 5* Cause of tne 0 0: Discuss wnat tne Ot C was cue to. e.g a program crencown, new regulation analysis or oesign
[ Jrror, test resusu snowing a oeficiency. and/or failure to meet cesign criteria and/or pur: nase specifications. In:!uce
.. d.
- calculations. analysis resutu, test results, ancior pur nase recuiremenu not met.'er einer bases. (See Note S.)
S. Consecuences on Plant Desien 8 unctions: Discuss ettees of failures on all invosved component *s, structure's, and system s aminty to perform tnear plant cesign fun:: ions.- (Sec Ncte 10.) . g f, u . .
- f. w . .=bt. ,* -
.' ' '. / .? 7. . Jurtifi::stien for Cen:!usiens in Faiiure Evaiusti:n: Dis:uss :ne reas=ning cased en :ne information zoove wni n leacs
- k. 10 tne con sus Ons states. [See Note 11.)
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NOTES ON ER FORM B!.CCr.S *
- 1. Provide a oefinitive statement of the CAQ. The NCR/SOR oescrj= tion of the CAO is to be restated vercatim or expanced for clarification to ensure tne statement reflects "stancaione" cocumentation of the CAQ.
- 2. Various items in Part B (pages 2 and 3) are to be comcleted to succort :ne conclusions and re:ommen=ations. A!! items on :ne form (pages 2 and 3) are not ne:essarily amplicacie to ea:n CAQ. Add sneen and cata as necessary.
2, Explicitly state tne co,nelusions of :ne failure evaluation regarding tne ability of :ne affe=ted component's. stru=ure's. or system's capability to perform its recuired cesign fune: ion. 4, Re=ommen=ations in this block (or elsewnere on tne ER) should provice OE's best juegmen: as to what is neeoed to correr;:ne condition. Recommen=ations are to refle: suggestions that correscond to trae stated con:!usions of the failure evaluation. The re==mmencations should not be worced as re=uesting work autnori:stions or funding for additional work. .
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- 5. C:ner affe=ed : mpenents, stru::ures. and/or systems (CESS) not spe:ifically identified in Far: A of the ER should be icentified here. -
E. "Me:nanism" per:ains to ine me:nani=s of individual component failure (s). ,
- 7. Alternate Uses and Generi: imoli:stiens: Identify alternate uses of :ne affe=ed CS5s in the plant. If:ne :enditi:n has generi:impil:stiens. :ney sn=uld be dis =ssed here. .
. +.$ , . e, - 8. "Mcde" as used here pe::ains to cperati:nal manner or prc:ess. ~.:7]_ . ;~ . '* 9.
Self.exclana ory. - - -
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- 10. A cone.[usive ::stement is needed here on :ne ability of the affe=ed CSS to perform its intenced design fun = ion conchien ce=mented in ra:. A cf :ne ER. Plant safe:y asse:.s (i.e., safety evaluatien) are nc to be consiocred nere.
- 11 3 Provide ade uere ju::ifi::: ion to ensure the con:!usiens stated are legi:al and reasonable based upon the evalua.ien findings and :stements.
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Definitive S zterent of CAO ' OI has failed :o identify the =ini=u= re: cf design calculations necessary to docume::.elec: ical sys:e=s desig adecuacy. As a resul: of various audit fi= i: process, dingsvas agains: de:e =ined DI i=cludi:g tha: a INFO audi: ef :he 3ellefente design
=ini=== se: ef desig OE/elec: ical should fe==zily_ identify the calcula:ie s necessary to supper: c gei:g desig:
modificatic:s. Po:ential Ceneric Cc:dizio: Evaluations cante: be accurately made vi:hou: such a planned program fe: SQN. Exa=ples.of deficiencies bein6 iden:ified: -
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No doc =e :ed calculz:icus exis: :o evaluate 4807"C12ss II and ne:-Class II over and under vol: ages when power is bei:g supplied frem vzzicus ne:-se:=al align =et:s. Also, :here are no re::ievzble
- calculatic:s fer ::xh.:= cc :rol circui: cable leng:hs fe: :he .'fCC
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s:tzter circuits. ~his cc:di:ie:s exists fc: SQN but to prog z= is ~ underway to deter =ine if these calcula: ices are receired. . _. -,wan
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.me sz=evoltage as z _.. cc:di:ic:s es e.SkV shu:dern buses 2:d 6.9kV 30? buses.
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- 3. G: T'3539 .
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*~ is CAQ fc: UNinentified several ec=pc=e::s fed fr the 12071-C .
vital vol:zge i=st:=entper the power syste= vhich did =c: have adequate cperzting
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were focud to have adecuzte cpezz ing re=zi=ing His review did to: safety reizted A-C g- , p . ,
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r w .:. -. ce=:le:e review cf the 1207 A-C vital ins::.:=e : pcver svste= vas
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