ML20084N617
| ML20084N617 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/20/1984 |
| From: | Witkowsky F DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20084N610 | List: |
| References | |
| TAG-6.0, NUDOCS 8405170116 | |
| Download: ML20084N617 (49) | |
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4 DUQUESNE LIGHT COMPANY BEAVER VALLEY POWER STATION -
UNIT NO. 1 TECHNICAL ADVISORY PROCEDURE TAG 6.0
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'Rr.v uw 0F INPO DATA AND VENDOR TECHNCIAL SULLETINS l
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L 'N DUQUESNE LIGHT COMPANY Beaver Valley Power Station s APPROVAL SHEET -170MADMINISTFATIVE N TECHNICAL ADVISORY GROUP PROCEDURE x ~
, REVIEW OF INPO DATA AND VENDOR TECHNICAL BULLETINS
\ TAG 6.0
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OSC %
Review Date Superintendent Technical Services Rav. Pages Meeting '
Chief Engineer '
Approval Effective No. Issuedi No. -
{ Initials Data Signature Date Date 1 14 9 > -
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, BVPS - TAG 6.0 REVIEW OF INPO DATA AND VENDOR TECHNICAL BULLETINS l h- 1.0 PURPOSE 1.1 The purpose of this procedure is to ' provide a formal channel of information and analysis to the Station for INPO operation data and Vendor Technical Bulletins.
2.0 SCOPE 2.1 This procedure is designed to provide a method for the TAG to comply with 0.M. 1.48.9N, Operating Experience Feedback
-Selection Procedure.
2.1 To provide a cooperative implementation of the INPO and NRC joint agreement for operational data and analysis exchange.
2.3 This procedure provides a means for other station groups to respond to Operation Assessment Group Recommendations.
i 3.0 DEFINITIONS 3.1 SER. ! Significant Events Reports.
3.2 SOER : Significant Operating Experience Reports.
3.3 O&MR : Operation and Maintenance Reminders.
h 1 3.4 INPO : Institute of Nuclear Power Operations.
I i 3.5 STA :- Shift Technical Advisor. ,
3.6 TAE : Technical Advisory Engineer I 3.7 TAG : Technical Advisory Group l l 3.8 T.B. : Technical Bulletin I~
! 4.0 RESPONSIBILITIES
. 4.L The designated Technical Advisory Group member shall -
implement and comply with the requirements of this :
! procedure. I 1
. 5.0 PROCEDURE *;
5.1 Significant Event Report and Significant Operating I Experience Report Review. !
5.1.1 SER's are received at the Station via NETWORK. i l- The Chief Engineer also receives a quarterly SER Summary from INPO via the U.S. Mait t i
O ISSUE 1
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PAGE 1 0F S REVISION 5
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-w a m BVPS - TAG 6.0 REVIEW OF'INPO DATA AND VENDOR TECHNICAL BULLETINS (continued) th SOER's are transmitted to the Chief Engineer from INPO-by mail.
l SER's and SOER's are presented to the TAE for
. action.
~5.1.2 ~ The TAE or his designee shall retain the original SER or S0ER for the ra.spective log. A copy of all SOER's are forwarded to the Training Department for information and use after receipe from INPO.
A SOER log will be maintained to insure records transmittal.
5.1.3 The TAE shall designate an STA to evaluate the SER/SOER for applicability to Beaver Valley. All items in the SER/SOER are to be addressed. He shall enter the results of his evaluation and any subsequent recommendations on the "BVPS Technical Support SER/SOER Review" form (See Figure I). All
, references used in the evaluation should also be s.
noted on this form.
'_r' S~.1. 4 After evaluation by the designated STA, the !'
"SER/SOER is routed to all other STA's for review.
A copy of the recommended action;and a request for '
any additional comments will be attached to the-
-h i
SER/SOER. ,
!5.1.5 The TAE shall submit all reviewed SER/SOER's to i the Operations Assessment Group for final review during . their monthly meeting. Any SOER judged to Ha require additional OSC action will be submitted to ,
the OSC for review. The results of all reviewed [
SER/SOER's will be included in the OAG Monthly !
Report. Copies of the OAG Monthly Report will be l l transmitted to L & C, Maintenance, I & C, Training and Operations for information and identification of potential problems. Any problem judged to
- l. .
require Engineering action will'be submitted to i 7., '
l the Nuclear Engineering Department via an EM.
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5.1.6 The TAE' or his designee will maintain a permanent '
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file of all. SER/SOER evaluations and >
lj" ,- reccamandations resulting from the OAG review. l 1- , , 1 3 ,
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ISSUE 1 ,
. PAGE 2 0F 8 REVISION S
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BVPS - TAG 6.0 REVIE'l 0F INFO DATA AND VENDCR TECHNICAL BULLETINS (continued) 5.2 Operations and Maintenance Reminders Review.
{ 5.2.1 Operation and Maintenance Reminders are obtained via the NETWORK System. 0 & MR's are presented to the IAE for action. 5.2.2 The IAE or his designee shall retain a copy of the l 0 & MR for the 0 & MR log. 5.2.3 The TAE shall designate an STA to evaluate and process the reminders for applicability to Beaver Valley. He shall enter the results of his evaluation anc any recommendations on the
" Operations. and Maintenance Reminder Review" form (see Figure II). All references used in the evaluation should be noted on this form.
- 5. 2. 4 After evaluation by the designated STA, the 0 & MR plus the STA recommendation is routed to all other STA's for information and/or comments.
5.2.5 The TAE will submit all reviewed 0 & MR's to the Operation Assessment Group for final review during their monthly meeting. The results of all reviewed 0 & MR's will be included in the OAG Monthly Report which is transmitted.to appropriate Station groups for information and identification (]) of potential problems. Any problem judged to require Engineering action will be submitted to the Nuclear Engineering Department via an EM. l 5.2.6 The TAE or his designee will maintain a permanent file of all 0 & MR evaluations and recommendations resulting from the OAG review. 5.3 Technical Bulletin Review 5.3.1 T.B.'s are received at Beaver Valley Power Station
.by the Station Superintendent. The Station Superintendent transmits the T.B.'s to the Chief Engineer for review and attachment of the " Vendor Technical Bulletin Transmittal Form". .
5.3.1 The T.B. 's are then forwarded to the Licensing and Compliance Group for initial review against NRC Bulletins, Circulars and Notices. If the referenced item was previously addressed or is presently being addressed, the document and remarks are indicated on the attached transmittal form. After review by the L & C Group, the T.B. is sent to the Technical Advisory Engineer (TAE). ISSUE 1 PAGE 3 0F 8 REVISION 5
- . - -. ~ _ ,,- _ - , ev-n_n . , . . . . _m BVPS - TAG 6.0 REVIEV 0F INPO DATA AND VENDOR TECHNICAL BULLET!NS (continued) g 5.3.3 The TAE shall designate a Technical Advisory Group (TAG) member to review the T.B. against existing INPO documents (SOER's, SER's and O&MR's) as a cross-reference to determine if the subject of the T.B. is currently being responded'ro, or has been addressed at any previous date.
5.3.4 After evaluation by the TAG, the results of this evaluation shall be recorded on the " Vendor Technical Bulletin Transmittal Form." All 4 references used in the evaluation shall be noted on this form. If the item is adequately addressed and documented by either Licensing and Compliance or the TAG, the document will be submitted to the OAG for final review at a subsequent monthly meeting. If determined not to have been adequately addressed by the L & C Group or by the
. TAG', the T.B. will require additional work by the Testing and Plant Performance Group. The T.B.
will also require additional work by the Testing and Plant Performance Group if the OAG does not agree with the L & C Group or the TAG determination that it has been adequately reviewed. In either case, if additional work by the Testing and Plant Performance Group is required, the designated TAG member shall make a:
, copy of the T.B. and transmittal form and place it in the T.B. Log to remain as a temporary record of the TAG, evaluation *and return the original to the TAE.
5.3.6 The TAE shall forward the reviewed T.B. and its L associated transmittal form to the Testing and Plant Performance Group for further evaluation. s j 5.3.7 Following evaluation by the Testing and Plant Performance Group, the Vendor Technical Bulletin , will be returned to the TAE who will submit the results to the OAG for final review during their_ ; l monthly meeting. Following OAG review and " ! recommended approval, the temporary copies in the ,
', T.B. Log will be discarded and the original filed.
6.0 ATTACHMENTS - i l-6.1 BVPS Technical Support SER/SOER Application, Figure I 6.2 Operations and Maintenance Reminder Application, Figure II , t j 6.3 Vendor Technical Bulletin Transmittal Form, Figure III 1 ISSUE 1 PAGE 4 0F 8 REVISION 5 , e l
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7.0 REFERENCES
7.1 SAP, Chapter 16 7.2 Operating Experience Feedback Selection Procedure, 0.M. 1.48.9N 9 O
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ISSUE 1 PAGE 5 0F 8 REVISION 5
w -~- - ma m.m BVPS - TAG 6.0 REVIEW OF INPO DATA AND VENDOR TECHNICAL BULLETINS (continued) l DUQUESNE LIGHT COFTANY Beaver Valley Power Station BVPS Technical Suncort 'SER/SOER Apolication SER/SOER No. Recoamrendation Date Comment Response: C 4 0 .
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b References FIGURE I d ISSUE 1 ' PAGE 6 0F 8 REVISION S
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BVPS - TAG 6.0 REVIEV 0F INPO DATA AND VENDOR TECHNICAL BULI2 TINS (continued) ! DUQUESNE LIGHT COMPANY Beaver Valley Power Sec. tion Operations and Maintenance Reminder Aeolication O & MR No. Recommendation Data Comment Response:
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s - e 4 _ References l FIGURE II o l v ISSUE 1 PAGE 7 0F 8 REVISION 5
w_ _ , . . - n . x t BVPS - TAG 6.0 I REVIEV 0F INPO DATA AND VENDOR TECHNICAL BULLETINS (continued)
@- DUQUESNE LIGHT COMPANY Beaver Valley Power Station VENDOR TECHNICAL BULLETIN TRANSMITTAL FORM l T.B. No.
SUBJECT:
l I LICENSING AND COMPLIANCE REVIEW NRC Bulletin, Circular, Info Notice Cross-Reference Reference : Document Remarks : i i p
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Signature Date , i Send Reviewed T.B. and Form to the T.A.' ' TECHNICAL ADVISORY GROUP REVIEW i INPO Document (SOER, SER, O&MR) Cross-Reference Q Reference Document Remar,s x t j i Signature Date i Send Reviewed T.B. and Form to the T&PP Suoervisor. i l TESTING AND PLANT PERFORMANCE EVALUATION i Comment Resoonse: i i
. i L
References:
l l l L l Send Reviewed T.B. and Form to the TAE. ( FIGURE III l g* ISSUE 1 PAGE 8 0F S REVISION 5 i
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j NUCLEAR DIVISION DIRECTIVE NO. 4 l Corrective Acrien Systems e PURPOSE To cicarly identify the various and diverse systems which are utilized to identify, track and resolve items which require corrective actions to main- , tain or i= prove the safety posture or reliability of the Beaver Valley Power Station and/or to assure or i= prove its compliance with regulatory require-ments. APPLICABILITY Applies to personnel employed in the Nuclear Division. RESPONSIBILITY The applicable department heads are responsible for administering this directive. REQUIREMENTS .
- 1. A Maintenance Work Request (MWR) shall be issued in accordance with
'u ' the Maintenance Manual to initiate correct'ive or preventive maint-anance activities on installed station equipment. All MWR's shall be tracked using the computerized maintenance planning system.
- 2. A nonconformance report (NCAR) shall be issued in accordance with _
the OQC Manual to initiate corrective action for nonconforming equipment, material or, activities. The Director of Operations Quality Control is responsible to track NCAR's to completion.
- 3. The Onsite Safety Committee shall identify and initiate appropriate corrective actions (MWR, SMR, OMCN, or MMCN) for matters which are reviewed by them. These matters include Incident Reports, INPO SOERs, Vendors Bulletins, and items from IE Bulletins, Circulars and Notices referred to the OSC by the Superintendant of Licensing and Compliance.
- 4. The OSC is responsible for tracking to completion all items for which -
they have initiated corrective action that is not tracked within another tracking system.
, 5. The Superintendant of Licensing and Compliance is responsible for tracking to completion all items related to NRC and QA identified items which require corrective action.
- 6. The Licensing and Compliance Section is responsible for the preparation, s
review, evaluation and verification of all responses to the NRC. ISSU~ l 10/12/81 O
NUCLEAR DIVISION DIRECTIVE NO. 4 REQUIRDIE2iTS (continued)
- 7. An Incident Report shall be prepared for abnornal events as described in the Station Adminstrative Procedures. The details of the incident must be evaluated _and corrective actions specified. These corrective actions must also be tracked by the OSC if not tracked within another tracking system.
- 8. The Offsite Review Committee is responsible for initiating investigations .
and recommending corrective actions for matters which involve significant safety concerns or chronic failures and/or repetitive occurrences of equipment failure or personnel error. Nuclear Division Review: if/I . , Nu ear Support
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Nuclear Operations Nuclear Safety / Nuclear ervices - and Licensing Engineering v i i
-Quality Assurance Review:
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Approval: ~ l Vice PNasid/nt-Nucleat/ '
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i L i i b y ISSUE 1 10/12/81 - f a
I l' 2. NPRDS/SEE-IN f Each utility should indicate or reaffirm its active participation in the i NPRDS and SEE-IN programs. The utility should supply the necessary basic ! information and should report failures and problems on a timely basis. Adequate internal controls should be in place to ensure that this activity is . timely, consistent, and controlled and should include incorporation of future revisions to these programs. Response: BVPS-1 will continue to participate in the NPRDS and SEE-IN programs. Failure reports are submitted to INP0 in accordance with the reporting criteria set forth in the Reporting Procedures Manual for the Nuclear Plant Reliability Data System (INPO 84-011). Site Administrative Procedures ensure failure information is forwarded to the Planning and Scheduling Group (per the Maintenance Work Request Forms). Planning and Scheduling Procedures ensure that failure-related information transcribed from Maintenance Work Request forms is reported on NPRDS. Information received from the SEE-IN program such as Significant Operating Experience Reports, Significant Event Reports, and Operations and Maintenance Reminders is ensured a review by Technical Advisory Procedure No. 6, Section 5. Future revisions to the NPRDS and SEE-IN programs will be reviewed for incorporation into existing procedures.
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DUQUESNE LIGHT COMPANY
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Nuclear Divisica Site Administrati*te Procedures CHAPTER 3D THE MAINTENANCE WORK REQUEST Chapter Index *
- Page
'I. PURPOSE .1 II. A'PPLICABILITY 1 t
III. DEFINITIONS 1 IV. RESPONSIBILITIES 2
- V. REFERENCES -
2 VI. INSTRUCTIONS A.1 Function 2 A.2 General Rules 3 A.3 Flow Path 3
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APPENDIX MWR Flow Path Figure 1 MWR Sec. 1 thru 3 Figure 2 . MWR Sec. 4 Figure 3 Detail Instructions A.2 thru A.14 NPRDS Codes - B-1 thru B-3 : k
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, DUQUESNE LIGHT COMPANY Nuclear Division Site Administrative Procedure CHAPTER 3D THE MAINTENANCE WORK REQUEST I. PURPOSE .
The purpose of this procedure is to describe the Maintenance Work l Request and Failure Report Form 100 as a vehicle for initiating corrective action maintenance. II. ' APPLICABILITY i This procedure applies to all personnel who initiate, review, approve, complete, assign reference numbers to, and maintain an i indexed file of Maintenance Work Requests (MWRs). III. DEFINITIONS , A. Corrective Action Maintenance Maintenance action taken to . determine or correct 'any deficiency or non-conformance and l (g return equipment or systems to the originally intended y.,. function. B. Design. Change - Any change in structures, systems or compo- [ nents which requires a revision to a design output and which ( affects the safety-related functions (s) of those structures, ; systems or components. l t C. Maintenance grouc - For the purpose of this procedure, l Maintenance group implies both the Maintenance and Instrument t and Control groups. The following are definitions for the purpose of Section VI, Instructions.
- 1. Maintenance Supervisor: Refers to Maintenance or i
Instrument and Control Supervisors.
. 2. Senior Maintenance Engineer: Refers to Senior Mechanic- '. ,
al, Electrical, I&C or Computer Engineers.
- 3. Maintenance Engineers: Refers to Mechanical, Electrical I&C or Computer Engineers.
- 4. Mafntenance Foreman: Refers to Mechanical, Electrical IEC or Building Foreman.
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Nuclotr Division - Site Adninistrative Proescura Chapter 3D III. DEFINITIONS (Continued) C. 5. Planning & Scheduling Senior Engineer: Refers to Senior PSS Ou age and non-Ou: age engineers.
- 6. Planning & Scheduling Engineer: Refers to Electrical, Mechanical, I&C, Construction, and Testing, Planning.
Engineers. D. Maintenance Work Request and Failure Recort Form - A fermal document used to report deficiencies which require corrective action' maintenance. A copy of the form is shown in - Appendix A, Figures 2 and 3.
- E. Work Package - consists of the. MWR, written procedures or work instructions, Material Requisition Slips, and any other documentation required to perform a particular maintenance task.
IV. RESPONSIBILITIES - A. For the purpose of this procedure, responsible individuals are identified in the instructions section. V. REFERENCES . A. Beaver Valley Power Station Conduct of Maintenance Manual u [) _ (MM). B. Beaver Valley Power Station, Station Administrative Procedures, Chapter 8: Maintenance.
. C. Beaver Valley Power Station Quality Assurance Plan.
VI. INSTRUCTIONS A. General ,. 1. The primary functions of the MWR are: to initiate' l corrective action maintenance, to identify any l procedures or tests required to correct the deficiency, i and to indicate the need for Quality Control (QC) i coverage. Secondary functions include serving as a record of equipment operating and maintenance history, as an aid in manpower and cost planning, as an aid in '. [ scheduling, and as an aid in predicting the need for changes in a Preventive Maintenance Prcgram. l 2. The following general rules apply to all personnel who record information on an MWR: l n~ t .
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Page 2 of 7 Revision 0 t:
.i. . . ! P Nuclecr Division - Sito Administrative Proctdure Chaptar 3D
,m VI. INSTRUCTIONS '(Continued) h A. 2. a. Prenumbered 52's will be given to Operations, f
Maintenanca, and the ISC group. Unnumbered MWR's may be obtained from the Maintenance Clerk or ! Central File. , s !
- b. All applicable blocks shall be filled out-complete- !
}' ly; all non-applicable blocks must be marked "N/A". '
.(See the detailed instructions for applicability.) !
- c. Any incorrect entry shall be voided by a single -
f line through the entry. Inserted adjacent to the i 4 voided entry must be the corrected entry, the . initials of the person making the correction, and ' the date of the correction. Correction fluid and '
' correction tape are strictly prohibited. !
- d. The information shall be entered in black ink: it may be typed or hand printed but so as to be legible I and compatible for photo-copying. !
- 3. The following steps describe individual responsibilities !
as the MWR is processed through the flowpath depicted in i Figure 1. I k
- a. The' orf ginator, who may be any DLC BVPS supervisor i
%l or other responsible individual assigned by such a ! supervisor, shall fill out Section One of the MWR. ;
- b. A copy of the MWR may be retained by the Originator, 4
but the original and one photo-copy of priority 1 l through 3 MWRs shall be sent directly to ,
.- maintenance to be handled as specified in MM y ; Chapter A, Section II, Emergency Work. The !
original and one photo-copy of priority 4 through 9 i _ :MWRs shall be brought to the MWR review meeting l (held prior to the Daily Schedule Meeting in the '
. Station Conference Room). Or, the original and 1
, copy may be sent to the Planning and Scheduling i Group to be brought to the meeting. The Nuclear !
- Station Opetating Supervisor (NSOS) or his !
designated alternate (SRO) shall bring operations i group originated MWRs to the MWR Review meeting and i together with a Planning and Scheduling ,
. Representative shall review all MWRs with l
. priorities 4 through 9 for accuracy and' t completeness. At this meeting the NSOS or r designated alternate (SRO) will also determine the ;
applicability of the " Authorization to do Work" and ,
" Satisfactory Completion of Work" signature block. l The reviewed MWRs shall be distributed to I Maintenance Supervision during the Daily Schedule t -1 Meeting. ' ./ r Page 3 of 7 Revision 0 !
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_- . - - - - _ .. - . . . = Nucles: Divisica - Site Administrative Procedure Chapter 3D ; VI. INSTRUCTIONS (Continued)- t l A. 3. c. Maintenance Supervision shall perform the following: i
- 1. Void those WRs which are invalid, do not f contain sufficient information, or which (
duplicate another WR which is being ; processed. A copy of voided WRs shall be ; returned to the originator with a brief statement as to why the WR was voided and the ! signature of the individual who made the - I determination. (Example: VOID - Duplicatas l WR No. 82 7352, etc.) Original void WRs i shall be filed with completed WRs.
; 2. Determine whett.ar the request is a Maintenance l Task or a Design Change (DCP). If a DCP, !
follow the instructions in MM, Chapter A,
. Section 5b, otherwise continue. ,
- 3. Fill out Section 2 of the WR including additional werk instructions as applicable per l MM Chapter A, Section Sa. i
- d. Once Section 2 is complete the Maintenince Clerk
- .s '
loss the WR and sends a copy to the Planning and
, Scheduling Group for tracking. An Operations .
f;' Quality Control (0QC) Representative shall review i
. each WR and indicate the need for OQC coverage by ,
stamping, initialing, and dating the original. '
- e. Plann g and Scheduling will input the Tracking [
copy of the WR's into the WR Tracking Report. l This report will be used to assess the WR backlog i for maintenance. Status' will be determined as
-follows:
- 1. Open - WR has not been worked ;
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- 2. Complete Awaiting Paperwork (CAP) - if the WR is reported complete on the maintenance
! foremans report or if the NSS signs off the l satisfactory completion of work
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! 3. Complete - when section 4 of the WR (see l Appendix A Figure 3) is completed and signed ! off by maintenance. l L i i i
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Nuclear Division - Site Administrative Procedure Chapter 3D VI. INSTRUCTIONS (Continued) A. 3. e. The appropriate Maintenance Senior Engineers will perform a quarterly review of the L'R Tracking Report and Planning and Scheduling will make the appropriate revisions to insure che Reports accuracy.
- f. 51's will be, scheduled for operating modes and outage modes in the following way:
- 1. Operating Mode - . .
~ a) PSS engineer will develop a six day work schedule for his or her maintenance group.
b) The appropriate senior maintenance engineer or his designated alternate will review the preliminary schedule with the Planning & Scheduling Engineer for comments and revisions if necessary. c) The Planning Engineer . vill revise the schedule preliminary if necessary incorporating maintenance's comments. .m}
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d) The Senior Planning Engineer will ~~ conduct a Plan of the Week meeting on Thursday afternoon between the Station Operating Supervisor or his designated
, alternate, and the planning engineers to review and approve the next weeks work schedule for maintenance.
\
e) The Senior Planning Engineer will
. process the reports for the Daily Schedule Meeting and the Planning Engineers will update the reports on a daily basis.
- 2. Outage Mode a) The Planning & Scheduling Engineer will arrange the outage 5'R's into work ,
packages. ,q .jj Page 5 of 7 Revision 0
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Nuclear Divisica Site Administrativa Procsdure Chapter 3D - [ VI. INSTRUCTIONS '(Continued)
., A. 3. f. 2. b) The Operaticas Supervisor or his desig-nated alternate will review the work ;
packages for the validity of clearance ! points, priority of the 52, and system conditiens required to place the clear-l ance. I I c) The Maintenance Supervisor will review ' U the work packages for manpower, parts, , duration and any additional comments
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about the proposed clearance. ' d) Outage %'R work packages will be ! factored into the scheduled outage by , the Outage Senior Planning Engineer and : the Planning Engineer. I i e) Outage work packages for unscheduled outages will be brought to the Oper- ! ations Supervisor or his designated ; alternate after the plant parameters are determined for approval to -be incor-
, porated into the unscheduled outage.
- g. The Maintenance Engineer will forward the scheduled '
A. MWR's as well .as the additional support MWR's to-
/ the Maintenance Foreman so it can be worked. The L work is performed according to the procedures of l the Conduct of Maintenance Manual Chapter 1 l Section A.
?
- h. - After task completion, the person in charge of the i work party and the Maintenance Foreman shall fill i
. +:s out Section 3 of the work request. He will then l t forward the MWR and its associated documents to the Maintenance Supervisor or his designee for review
- l to determine that all requirements have been satisfied and that all non-conformances have been ,
properly resolved. l t [ . - l i i I [ 1 i l ;
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Nuclear Division - Site Ad=inistrative Precadure Chapter 3D ' 3 VI. INSTRUCTIONS (Continued) A. 3. 1. The Maintenance Supervisor or his designee will ' forward the original copy of the L'R to the centrol ; room for the Shift Supervisor's signature. If the ; 5'R is to be signed off pending scme post mainten-ance testing, then the L'R will be placed in a MPS (MWR Pending Signature) file in the control room i until such time that its ready for Shift Super- , visor's signature. After the MWR is signed off it , will be placed in the MSO (MWR's Signed Off) file 4 - I the control room and will be picked up . by the . operation's representative "to the morning meeting l for distribution back to maintenance in the morning meeting. Those 5*R's that are signed off immedi-
. ately will be returned to maintenance immediately.
- j. The appropriate Maintenance Sub Group provides a supervisory review of the co:npleted work package and fills out Section 4 of the MWR.
- k. The Maintenance Clerk logs the MWR as complete, j forwards a copy to the Planning and Scheduling Group (for updating the MWR Tracking Report), and files it in the maintenance files ,(for CAT II and III HWRs); or for CAT I MWRs transmits it along witir all maintenance - originated / controlled supporting S ' documents (eg., CMPs, MSPs, Material Requisition !
O slips, Store Dept. " Accept" tags, etc.) to the : Document Control Center. Supporting documents such I
. as OSTs, QC General Inspection Reports, etc. shall *
- be transmitted to the Document Control Center by
- the associated originating group and filed these
-1 separate from the MWR.
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Nucicer Division - Site Administrative Procedure Chapter 3D APPENDIX A - DETAILED INSTRUCTIONS SECTION 1 - ORIGINATOR (SIDE 11 CARD 10 t Columns Field Name Insttuctions 10 . Transaction Leave blank, this space will be
~
filled in when the computer- . i ized history file is updated at later date. , 11, 12 Unit Enter the number one (01) to , identify Beaver Valley Power ,
. Station Unit 1.
13, 14, 15 System No. Enter the system Chapter Number so that the Number is in columns 13 and 14, and the
- g. -
Chapter Subdivisions are in 3 column 15. (Example: 05A)
- j ~
NOTE: For computerized filing Y purposes, the only _D Chapter Subdivisions used are OSA and 05B. k
.;.. 16 thru 28 Equipment Mark No. Refer to the Master Equipment i
. 47
,- List (MEL) and enter the mark number of the equipment to be 3 .
worked on, (not for the larger
,.' piece of equipment with which it may be associated.)
For instance, an MWR was written identifying AS-E-1A (1A AUX BOILER), problem; , sightglass leaking. The MWR should have been written for LG-AS201A (1A AUX BLR WATER DRUM LEVEL). a Page A.2 Revision 0
Nuclear Division - Site Administrative P ccadura Chapts: 3D Columns Field Name Instructions 16 thru 23 Equip: tent Mark No. Maintenance History Tracking and Reliability Data Reporting are dependent upon the spe-cific Mark No. for each component in DLC computer programs. If an inaccurate Mark No. is given as above, this tracking and reporting ability is lost unless valu-able time is expended to go - back and research the proper equipment mark number. This field must never have more than one piece of equipment identified. If work is to be performed on two like pieces of equipment, having different mark numbers, a separate work request must be prepared for each. An Equipment Mark No. of N/A or MISC should be used eniv when the item to be worked on has no Equipment Mark No. - rw l} 5* 29 thru 68 Equipment Functional Enter the name of the equipment or describe the equipment, if unnamed. The MEL should be used as a reference. 69 fQACat. Enter the Quality Assurance
~,' . .. category of the equipment as Indicated in the MEL.
+ '
NOTE: If the' Equipment Mark No. is N/A or MISC use
, QA3.
~
CARD 11 10 thru 15 Request No. MWR identification number (to be entered by the Maintenance Clerk). , t i i i y : [ Page A.3 Revision 0 - l l
~ _ _ - __ _. _. _ . . _ _ _ - _ . _ . _ _ _ _ _ _ . _ _ . - _ . _ . . . . . _ . _ . _ . , , . - _
r1 I W Nuclear Division - Sita Administrative Procedure Chaptar 3D Columns Field Name Instructions
~ '
16 thru 25 Request Data Enter the date and time the request is initiated (Alw.tys use the 31 hour clock for time 0000 thru 2359). 26 thru 35 Failure Started Enter the date and time ::he problem was first noticed. 36 thru 45 - Tech. Spec. Date If applicable enter the date if Required and time in which the work must - be ccmpleted to preclude vio-lating a Tech. Spec. respense time requirement. If not applicable mark "N/A". ' 46 thru.51 These columns have inton-tionally been deleted. 52 thru 57 Design Change No. If applicable, enter the engineering Technical Eval-
, , untion Report (TER), Station Modification Request (SMR), or
- Design Change (DCP) number related to the work to be performed. (To be completed by D
the Senior Engineer at a later U date.) If not applicable, mark N/A. 58 Priority Code Enter one of the following code numbers, as applicable: c
>-M , 1. CRITICAL ITEM - Items in
~
this category will be ex-pedited at the expense of items in all other cat-escries. Failure to com-plate a priority No. 1 item will result in a
." Tech. Spec. Limit Violation.
Page A.4 Revision 0
7 Nuclear Divisica - Sito Ad:ninistrative Procedura Chaptar 3D m Columns " Field Name Instrue:iens
~
58 Priority Code, 2. DEMANDS IMMEDIATE A'ITENTION - Failure to complete cre-ates a safety hazard or could damage plant equipment.
- 3. COMPETE AS QUICKLY AS POSSIBLE -
Failure to i
. complete will restrain imminent Start-up.- -
- 4. COMP G TE WITHIN SEVEN DAYS -
Affects power generation ! which could result in i re.duced power or in plant
. shutdown. ,
- 5. COMPLETE WITHIN 30 DAYS -
Failure to complete could ; result in loss of system t operation.
- 6. COMPLETE WITHIN 60 DAYS -
, Failure to complete could.
result in loss of system i D L_/ redundancy. '
- 7. ,
COMPLETE WITHIN 90 DAYS - Reduces the efficiency of : the system involved.
'. 1
- 8. COMPLETE BEFORE THE NEXT I
CHANGE OF SEASONS - Af-A- facts the operation of ,
.- the system only during ,
, 3. , , the seasons it is used in, t
'.. / 9. COMPLETE AS MANPOWER AND
/~ ' MATERIALS ARE AVAILABLE [
.- AFTER HIGHER PRIORITY JOBS :
ARE COMPLETED l t N,. - l Page A.5 Revision 0 l I
--r e-~-. .-, .- ,--- . . . - . . . . . . . - , - - - - , - , ~-,-e.- - , - - n,.
r --..-,-,r,,-w., .e--- ,,,--.,,,en p. , . ~ ~ - - - - , , , - - - . . . -
Nuc1ccr Division - Sits Administrativa Procedars Chapter 3D _ Columns Field Name Instructions 59 Plant Mode Enter the plant mede during which the work could be performed. (Choose One)
- 1. PCVER OPERATION
- 2. STARTUP
- 3. HOT STANDBY
- 4. HOT SHUTDOWN
- 3. COLD SHUTDCWN
- 6. REFUELING
- 7. ALL MODES
- 8. PRE-REFUELING No Column OPS Failure Action If applicable, operations may
. Number identify any tags or stickers which are to be removed upon
, completion of the work (eg.,
Jumper / Lifted Lead Tags, 0.0.S "S stickers, etc.) If no action _.' mark N/A. CARD 12 Mark the codes by blacking in
; . the X:
10 thru 17 Effect of Failure Mark the code (s) which best de-System scribes the full effect this failure had on the system (s). 18 thru 24 Effect of Failure Mark the code (s) which best de-Plant scribes the full effect this
, failure had on the plant.
25 thru 35 Failure Detection Mark the code (s) which identi-fies how the f ault was found. . 36 thru 43 Status Mark the code which best describes the status at the time of failure. Where the system and subsystem status codes both apply, use the subsystem code. w Page A.6 Revision 0
s -
~~,._ , ,
, Nuclear Division - Sito Administrativo Proceduro Chaptor 3D
. t N Columns Field Name Instr:.crions NO CARD Nt'MBER < ,
Initial Problem - ,. 4
,- Fully. describe the problem or or Failure Description failure which prompted the i s , generation of the Work Request. This information N
will not be entered into the
,, o -
computer program; however, it will be used as supplementary
' ,. ~
information for completing . cards 33 thru 36 (Reverse side
, x
,,, cfs Form 100) for input to the
.'s( , NPRD System.
Location l' Describe the location of the I ' equipment / component. Post Maintenance Identify any post maintenance
' Test
- test (s) required. If none are s
applicable, mark N/A. s CARD 13 10 thru 49 Task Description Briefly describe, for tracking purposes, the problem or ] t,y , failure which request. prompted the
- s. -
t Originating Supervisor Signature of - the originator.
- By his signature the origin-
. ator verifies that the .WR was
, ,, initiated in. compliance with
. this procedu're and that all
. :L , information entered by him is
'.a
' " correct. A review of the form
, and the , preceeding instruc-
, tions is MANDATORY prior to '
signing. , SECTION 2 - MAINTENANCE (SIDE 1) c CARD 14 .
,_ . T-10 thru 13 Lead Group Mark the applicable box to inficate the group responsible y , f65 the wark' .
s ,
.. p.
\
3 d sb , A . Page A.7 s , Revision 0 k s A
Nuclect Divisica - Sits Administrativo Procedura Chtpt:r 3D Columns Field Name Instructiens No Column Budget Account If applicable, circle JO (Job Number Order) or CO (Csnstruction Order) as directed by the Budget Group. If not applic-able, mark N/A. > No Column Procedures and Tests Insert the number (s) of the Number Required procedure, test or other documents which will be used in
-the perfor' nance of the work. .
If not applicable., mark N/A. Additional Work Instructions Insert any additional instruc-tions necessary to supplement the specific maintenance procedures, tests, etc. which' will aid the persun performing the work. Reference appro-priate sections of the Maintenance Manual, DLC
, Accident Preventien Manual, etc. This section nay be left
. blank, or it may be extended by attaching an additional sheet.
D- Maintenance Supervision /Date Maintenance Supervision shall
, ,f review and verify the validity of the request by signing and dating it prior to submitting it for further processing.
. SECT *0N 3 - WORK PARTY (SIDE 1) ,
CARD 16 l 10 thru 19 Start Work Insert the date and time tho work effort was begun. i i 20 thru 29 Completion Date Enter the date and time the ,. work was actually completed.
. i D
.)
- Page A.8 Revision 0
, , , - - - , - - , . - , . , , , -,r-,-,----,,-4 r-- --,- ev. - - , -. ~-,-..-~.-,.--,,n, , - - , - ~ - - - - - - - - , - - - ~ , - , .
e : ; Nucle'ar Diviaion - Site Administrative Precedura Chapter 3D
., j Columns Field Name Ins t r.2ctions 3 / ,
30 thru 45 Actual Manheurs Enter the total nu=ber' of manheurs (to the nearest hour, I hour minimum) expended to - complete the work. If more than one maintenance disci-pline is required in :om-pleting the work enter the manhours expended for .sach discipline. All entries should be made using four . digits. For example: if two manhuurs were required by the Electricians and sixteen by the Mechanics tt.e entries would be 0002 in columns 30 thru 33, and 0016 in columns 34 thru 34. CARD 17 10 thru 27 Clearance No. Enter the Equipment Clearance Number (s), as applicable. If not applicable mark N/A. 28 thru 39 Matl. Req. No. Enter the Material Requisition
, Number (s), as applicable, for any material, spare parts, etc. which was required to complete the work. If not
' applicable mark N/A.
NO CARD Nm!BER Rad Work Permit No. If a Radiation Vork Permit is required in order to perform the work, record the permit number in this section. If not
. applicable mark N/A.
Cause and Corrective Action Write a brief, concise des-cription of the cause and the corrective action taken to complete the work generated by . the Work Request. Addition-
- ally, list the I.D. No. and calibration dates for any controlled meascring devices used (if not already listed on data sheets as an attachment to the MWR) .
n Page A.9 Revision 0
r- - l-Nuclear Division - Site Administrative procedurs Chapter 3D
- m. Columns Field Name Instructions Shif t Supervisor /Dat a If not marked N/A in the $R (Authorization to do work) Review meeting, the Nuclear Shift Supervi.sor (NSS) shall sign and date this block to authorize work to begin. .By his signature he verifies that the equipment to be worked on is in a safe condition from an operational standpoint (eg:
breakers are open and tagged, - valves are isolated and tagged, etc.). In those cases where the NSOS or designee has indicated "N/A". and has initialed and dated the block, no signature is required. Leadman/Date The person in charge of the work party will sign and date the request upon completion of the work. Maintenance Foreman /Date The lead craft foreman will review Section 3 of the form for completion of appropriate
, entries and signify and dating E' the request.
Shift Supervisor /Date If not marked N/A in the WR (Satisfactory Completion Review meeting, the NSS shall of work sign and date this block after all required tests are per-
, formed and the equipment has l 'been restored to his sat-
_ is faction. If the " Shift Supervisor (Authorization to do work)" block was marked N/A by the l - NSOS or designes, (SRO) then the cognizant supervision (the j originator or his designee) l shall sign and date the " Shift , Supervisor (Satisfactory Com-plation of Work)" block. r , Page A.10 Revision 0
Nuclear Division - Site Ad::linistrativa Procsdura Chapter 3D SECTION 4 - MAINTENANCE REVIEV (REVERSE SIDE 2) Columns Field Name Instructiens NO CARD NUMBER Question 1 Insert an "X" in the Yes box if the Work Request is a result of a change in design or indicates a change in design. If not, place and "X" in the @ box. - Question 2 Insert an "X" in tha Yes box if the Work Request indicates that a Systect or a cocrponent has failed. If noc, place an "X" in the @ box. CARDS 33 Thru 36 i e 10 thru 51 Failure Description The applicable Maintenance Personnel will enter an abbre-viated description of the '
, problem or failure from infor-mation obtained from Side 1.
. Section 1, " Initial Problem or O Failure Description". This '
V description must be concise and complete since it will be used for entering into the , computerized Nuclear Plant Reliability Data System cl_ (NPRD). CARDS 37 Thru 40 10 thru 51 Cause of Failure The applicable Maintenance Personnel will enter a brief
' concise description as to the ;
cause of the failure. Utilize information recorded on Side 1, Section 3 "Cause and Corrective Action".
- y. .
Page A.ll Revision 0
~
Nuclear Division - Site Administrative Procedure Chapter 3D CARDS 41 Thru 45 Columns Field Name Insr uctiens 10 thru 31 Corrective Action ~~ ne applicable Maintenance Personnel will enter a brief concise description as to the action taken to correct the problem. Utill:e information recorded on Side 1, Section 3 '
"Cause and Corrective Action".
CARD 45 - Mark the codes by blacking in the "X": 10 thru 15 Type of Failure Mark the applicable code (s) to characterize the type of failure. 18 thru 30 Cause of Failure Mark the applicable code (s) Category which characterizes the cause of the failure. 33 thru 60 Cause of Failure Mark the appliccble code (s) Description which best describes the cause m of the failure.
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b# CARD 46 10 thru 29' Mode of Failure Mark the applicable code which
' ' best describes the mode of failure.
32 thru 47 Action Taken - Mark the applicable code (s) Corrective which describes actions taken to correct the failure event. 50 thru 58 Action Taken - Mark the applicable code (s) Documentation / Followup which describes other records which may be available for study or those forwarded to others for assistance in evaluation. . i 3 ~} U . Page A.12 Revision 0
s. Nuciscr Division - Site Administrative Procedure Chapter 3D CARD /-8 . Columns Field Name Instructions 10 and 11 Question 3 Place an "X" in the YES box if an NPRD Report is required, if not "X" in the @ box. NOTE: If an NPRD Report is required, the darkly outlined codes on lines
- 12, 45 and 46 should not be used.
12 thru 21 Failure Ended Enter the date and ti=e of the actual end of the failure. Normally this will be the work completien date shown in Section 3 of the form; how-ever, in some cases completion of the work will not , necessarily signify the fail-ure has ended. For example, if i a temporary repair were made
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the failure ended date would be left blank.
, 22 thru 27 NPRD Component Code Enter the appropriate cede per V . Appendix I, attached. ,
28 thru 33 - Licensee Event Report Enter the date when a Licensee
'- Event Report is submitted, when applicable. .
NO CARD NUMBER Questions 4, 5, 6 and 7 Place an "X" in either the Yes , or & box, as applicable. l Type of Follow-up Action Write in any required follow-l and/or Reviewers Comments up action necessary and any I comments pertinent to the work performed. l ' Maintenance Engineer /Date Sign and date the form to ". l - indicate completion. 1 ? i L ..s - '.\ L-J Page A.13 Revision 0 i
s Nuc1c; Divicion - Sits Ad=inistrative Proc 2 dure Chap:cr 3D Columns Field Nane Instructiens
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Maintenance Supv. Review /Date The Maintenance Supervisor or designee will review the co=pleted Work Request and signify his ccacurrence by signing and dating the form. Review /Date The two additional review spaces provided on the form shall be used for sign off by other departments whenever - deemed necessary by the Maintenance Supervisor. I:% -1 V
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DUQUESNE LIGHT CC.'!PANY _, Nuclear Division Nuclear Support Services Department Budget, Plannine & Scheduling 5!anual CHAPTER 23 Nuclear Plant Reliability Data System I_ . PURPOSE The purpose of this procedure is to provide general information for ; the use and administration of the Nuclear Plant Reliability Data (NPRD) System. I APPLICABILITY The NPRD System is applicable to the following guides or standards: A. ANS Trial-Use Guide: Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants, N212-1973 (ANS-22). ,,, B. American National Standard Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants, ANSI w- N18.2-1973.
-C. ANS Trial-Use Guide: Nuclear Safety Criteria for the Design of Stationary Gas Cooled Reactor Plants, N213 (ANS-23).
D. IEEE Std. 380-197S: Definition of Terms used in IEEE Standards on Nuclear Power Generating Stations. III DEFINITIONS Not applicable to this procedure. IV SCOPE
- The NPRD System produces reliability and failure statistics on -
comp,onents and systems related to nuclear safety and balance-of-plant systems. Such statistics are for use in deriving reliability data of interest to operators and designers of nuclear power pla: reactor manufacturers, architect-engineering and con-structor firms and regulatory agencies. Revision 1
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.- NSSD - 3/PSM Chapter 23 ... Ij[ SCOPE (Continued)
The scope of reportable items under the NPRD system, in general, includes those systems and components necessary for keeping balance-of-plant and nuclear safety. Some types of systems and components designated in Safety Class I cr 2 are excluded frem the NPRD system scope of reportable items for pressurized water reactor type units. These are: A. Spent fuel storage systems and components. B. Reactor pressure vessel internals. 4 C. Structures and components for structures. D. Piping, fittings and valves in pressurized water reactor systems one (1) inch or less, nominal pipe size. For guidance, the following types of systems, and ccaponents within these systems important to nuclear safety and balance-of-plant, are included in the NPRDS reportable scope: A. Reactor coolant systems including pressure vessels. B. Emergency core cooling systems. [* C .~ Decay heat removal systems. D. Reactor protection systems.
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E. Reactor containment and pressure suppression systems. F. Reactor containment isolation systems. G. Reactor containment emergency cooling systems. H. Reactor containment spray systems. I. Reactor containment hydrogen control systems. J. Those components of control rod systems which are necessary to render the reactor subcritical. K. Initiating systems required to acccmplish safety functions,
-including emergency core initiating systems and containment isolation initiating systems.
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. NSSD - 3/PSM Chapter 23 IV SCOPE (Continued)
L. Condensate M. Feedwater N. Main Steam O. Diesel Support Systems
-P. More I&C Equipment (switches, relays, etc.)-
V RESPONSIBILITIES The- ' Associate Engineer is responsible for reviewing all Maintenance Work Requests (MWRs) and Licensee Event Reports (LERs) for inclusion in the reportable failure data as defined by the NPRDS Reportable Scope Guidelines. The Associate Engineer is responsible for obtaining the NPRDS Reportable Failure Data from the Maintenance History Progrdm and submitting the information to the NPRDS Contractor. The Associate Engineer is also responsible for receiving and maintaining the reports from the NPRDS contractor and will maintain liaison with the DLC Data Processing Department and the NPRDS contractor. X INSTRUCTIONS A. . General Imolementation When r the ' corrective maintenance requested b' y the MWR is complete and the Maintenance Department submits the completed
.- . MWR copy' to the Associate Engineer, the Associate Engineer will review the MWR for - inclusion in the NPRDS Reportable Failure Data and the information is keypunched and submitted to the Maintenance Historical System. As a result of the input to ;the MHS, if the failure is NPRD reportable, i,e. , the failure is'within the scope of that listed-in Step III of this procedure, the Maintenance History System prints out the NPRD i
- Report of Failure. An NPRD Report of Failure Form (NPRD-4) is filled cut from the information given and keypunched. The cards and subsequent edit report are then sent by mail to the NPRDS contractor. The information supplied to the NPRDS .
contractor is combined with information submitted from other operating nuclear power . stations and reports are issued by mail to the Associate Engineer from the NPRDS contractor. See
. Figure 23.1 for a flow diagram of the NPRD System.
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SSSD - 3/PS?! Chapter 23 H INSTRUCTIONS (Continued) L Routine inputs to the SPRDS contractor are as follows:
- 1. Quarterly Operating Reports (QCR) - As the name implies , ,
the QOR is submitted by the Associate Engineer to the NPRDS contractor quarterly, within 30 days after the end of the reporting quarter. The report includes unit ; service-hour information and is used to update the service-hour base for the systems and components contained in the data base. The QOR is based on the , Operating Data portion of the !!onthly Operating Report to the SRC.
- 2. Failure Reports - As noted above, primary input to the NPRDS is the information supplied on the WR. From this information, reports are generated by the !!aintenance History System in the format required by the NPRD contractor. The reports contain information with regard to a description of the failure, cause of the failure, failure type, corrective action, etc. If the component failure also.results in a system failure (recognized by the inability of the system to perform one or more of its required safety functions), then a Report of the Failure for the system is submitted as well as a Report of
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Failure for the component. The failure data cards together with the Edit _. Report for the cards, are sub-
'mitted to the NPRDS contractor by the Associate Engineer _
within 30 days of the end of the month in which a failure ,
- occurs. . However, when information is incomplete or uncertain,' the report. may be delayed until the '
information required to accurately complete the report is available. Reports may also be revised if more information becomes available after an original report
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is submitted.
!B. Data File >faintenance Data file maintenance is performed routinely by the NPRD i
-system contractor. Computer routines are provided to allow
- addition, replacement, correction, expansion, or deletion.of any record in the main file, including reports of failure.
Each participating utility is sent a listing of its submitted - system and component descriptive engineering data, for each reporting unit, after such data have been entered 'into the NPRD system data file. Input source documents are retained on file by the NPRD system contractor. Revision 1 f;'
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. .0 NSSD - 3/?SM Chapter 23 E INSTRUCTIONS (Continued)
C. System Outen:
- 1. Routine Output Reports
.The. following reports are prepared by the NPRDS contractor and distributed to program participants.
- a. Quarterly Report of Engineering Data for Individual Reporting Organizations (NPRD Report QOl)
- b. Quarterly System and Component Failure Listing (NPRD Report QO2)
- c. Quarterly System and Component Failure Listing for Individual Units (NPRD Report QO3)
- d. Quarterly Report of Component Failure Summary (NPRD Report Q04)
- e. Annual Report of System Reliability for Individual Reporting Organizations '(NPRD Report A01)
, f. Annual Report of System Reliability (NPRD Report
_ A02) 'T
- g. Annual Report of Component Reliability (NPRD Report A03) h .' Annual' Report of Cumulative Component Reliability
. for Individual Reporting Units (NPRD Report A05)
' 2 .' She'cial Requests Upon request, reports involving extraction or analysis of data from the NPRDS data base may be prepared.
'Information is retrievable on subsets of the data based on combinations of the engineering data, failure data, and control data fields, and on selected portions of these fields.
Typical analyses can provide:
- a. Mean time between failures
- b. Failure rates
- c. Average failure cutage duration Revision 1
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. NSSD - 3/PSM Chapter 23 ,
H INSTRUCTICNS (Continued) I C. System Outout (Continued)
- 2. Special Requests (Continued)
It is the responsibility of the person requesting the , report to define the analyses to be performed. The NPRDS ' contractor is responsible for translating approved requests into appropriate computer programs to generate the required output reports. All reports received from the NPRDS contractor are kept on file by the Associate Engineer for the review by Company personnel. VII RECORDS A. All records are maintained by the NPRDS contractor. B. The NSSD Planning & Scheduling Group receives a copy of the reports (from the NPRDS contractor) listed in Step V.C of this procedure and maintains a file of them. VIII REFERENCES A. Reporting Procedures Manual for the Nuclear Plant Reliability Data System. (Prepared by Southwest Research Institute per ANSI Subcommittee N18-20) B. "PRDS Reportable System and Component Scope Manual g FIGURES AND A'ITACHMENTS Figure 23.'1, NPRD Information Flow Path Revision 1
MAINTENANCE d et ASSOCIATE ENGINEER, ASSOCIATE ENGINEER ASSOCIATE ENONJEER
- ENGINEER O COMPLETE 8 NPRD REVIEWS AND INPUT 8 E FILLS OUT NPRD-4 RELATED MWR INFORMATION: INTO FORM FROM NPRD 4 8UDMIT8 NPRD-4 p 1
COMPUTER MAINT $ REPORT OF FAILURE FORM TO INFORMATION d , HISTORY SYSTEM g 811EET (FROM - KEYPUNCH g COMPUTER) 4 V i i NPRDS CONTRACTOR i ASSOCIATE ENGINEER NPRDS CONTRACTOR
- d , [ DATA STOR AG'T El PERFORM NPRD EDIT 2 l l PROGRAM AND > ^ ^'
> CORRECT ERRORS AND DEVELOP 8 AND I
{ 3 ENDS CARDS TO NPRD su CONTRACTOR
- ISSUE 8 REPORT 8 i
m S 5 a aa a a n s a DATA FROM OTilER UTILITIES ! , REPORTS BENT BY MAIL hr j PLANNING SSCilEDULINC i COORDINATOR I N RECEIVES AND l SENDS REPORTS TO j RECORDS MGMT SUPERVISOR FOR g FILING g 4 l E< 3 l @ FIGURE 23.1 y j NPRDS INFORMATION FLOW PATH g
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- 3. Other Vendors Each utility should continue to seek assistance and ETI from other safety-related equipment vendors when the utility's evaluation of an equipment or ETI problem concludes that such direct interaction is necessary or would be beneficial. These programs and those of lesser significance will continue to be reported by means of the NPRDS and/or the SEE-IN programs.
' Response: BVPS-1 will continue to seek assistance and Equipment Technical Information (ETI) from vendors when necessary or beneficial.
Correspondence providing ETI from vendors will be evaluated and resolved in the same manner as - other ETI by the Nuclear Engineering and Construction Unit. A Nuclear Group Directive (NGD) on Correspondence Control administrative 1y controls this activity. The NGD on correspondence control is being reviewed and will be forwarded upon approval.
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- 4. Internal Handling of Equipment Technical Information 1The . utility should process incoming ETI so the objectives noted below are achieved. ,
. - Administrative. procedures should provide control of incoming ETI whether it arrives directly from the vendor or from other industry or regulatory
' sources (i . e .' , NUCLEAR NETWORK, NPRDS, SEE-IN, NRC bulletins, etc.), so it receives the appropriate engineering / technical review, evaluation, and !
distribution for the following: prompt warnings to key personnel timely. incorporation into maintenance or operating procedures, equipment data / purchasing records, and training programs *
-future procedure review and revision cycles !
notification on NUCLEAR NETWORK of significant ETI i The incorporation of such safety-related information (or changes) remains within the scope of the utility's review and approval requirements. - Response: A . Nuclear Group Directive (NGD) on Correspondence Control assigns .; responsibility to the appropriate group or section for ! engineering / technical review, evaluation and resolution of . incoming Equipment Technical Information- (ETI). The NGD also requires each- group or section to develop procedures to provide tracking and dispositioning of ETI received as well as:
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prompt warnings to key personnel. timely incorporation of pertinent ETI into procedures notification to the Nuclear Engineering and Construction Unit :
'for revision of equipment technical manuals; and notification f to Training.for possible changes.to the training program notification to . the appropriate section head .of !
recommendations to improve the safety or efficiency of plant , operations ! t 5 A Site Administrative Procedure (SAP) defines the flow path of ETI ; received and the content of group procedures on review and l resolution of ETI. The SAP ensures consistent and controlled
. ! disposition of ETI. This SAP will be forwarded with the Nuclear Group Directive on correspondence control following their review ;
and approval. , , i t
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o The administrative program should require that maintenance or operating procedures cite appropriate ETI in the reference section of the procedure. Response: Procedures have been revised to instruct the procedures group to reference appropriate ETI when an Operational Surveillance Test, Maintenance Surveillance Procedure, Preventive Maintenance Procedure, Corrective Maintenance Procedure, or Calibration Procedure is changed. Within the performance section of the procedure, appropriate ETI should be incorporated and approved in the engineering, technical and quality review of the safety-related procedure. Response: All operating and maintenance procedures performed on QA Category I components are reviewed by the OSC for unresolved safety issues and approved by the Station Superintendent. s v -,
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- 5. Internal Handling of Vendor Service The vendor, contractor, or technical representative who will perform safety-related services should be a QA approved / qualified supplier of such nuclear safety-related services. Furthermore, the services should be specified in the procurement documentation so that a combination of procedural and QA/QC controls are established.
A vendor service may be performed using utility procedures. If so, the procurement documentation should specify that the service is performed using utility procedures that have been approved after a technical and quality review cycle typical for other utility service, maintenance, repair, or operating procedures. As an alternative, the service may be performed using - vendor or contractor procedures. In this case, the documentation should specify tha,t the service is performed using vendor, contractor, or technical representative procedures that have been reviewed and approved in accordance with the utility procurement program, QA program, and administrative review program. This is to ensure that their documents are processed and approved in 'a manner equivalent to the utility procedures concerning similar activities. In addition to specifying the procedures that will be used, the QA/QC program to be used should also be specified. The utility QA/QC program may be used. In this case, the procurement documentation should specify that the activity will be performed under the cognizance of the utility QA/QC program. Alternately, the vendor or contractor QA/QC program may be usee. In this case, the documentation should specify that the activity will bs performed under the cognizance of the vendor, contractor, or technical representative QA/QC program that has been reviewed separately and approved in accordance with the utility QA program. In addition, during the performance of the service, the utility QA program will monitor the effectiveness of their performance and compliance with its approved program , by suitable surveillance, inspection, and audit. Response: The ensire review of procedures prepared to address this issue has identified that additional administrative controls will be necessary due in part to a management reorganization which was made effective May 1, 1984. We will forward the revised precedures upon completion of the Onsite Safety Committee review of these documents. G
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- 6. Enhanced Programs NPRDS:
Each utility should incorporate the enhancements to the NPRDS recommeaded in Section 3.2. This could involve revisions to existing administrative programs or procedures. It also could require revised training or other actions needed to ensure a meaningful and effective implementation of the NPRDS program enhancements. SEE-IN: Each utility should incorporate the enhancements to the SEE-IN program recommended in Section 3.2. As in the NPRDS program, this could involve revisions to the existing administrative programs or procedures or to the training or other activities so the data reported to the SEE-IN program is complete and detailed enough to support the system enhancements being undertaken by INPO. Response: BVPS-1 'will work with the NPRDS user's group and INPO to achieve the goal of implementing the NPRDS and SEE-IN program enhancements. e
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