ML20136H282
| ML20136H282 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 08/07/1985 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20136H203 | List: |
| References | |
| P-12, NUDOCS 8508200251 | |
| Download: ML20136H282 (14) | |
Text
P-12
. Issue 1 E
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 11 (A j,Public iQ SerVICO PUBLIC SERVICE COMPANY OF COLORADO V
TITLE:
PLANT MAINTENANCE - MECHANICAL, ELECTRICAL, AND RELAY SHOP m
ISSUANCE r
N f), gW G 4 5(A)4dltbu b AUTHORIZED
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1.0 PURPOSE
- See Commitment 7.1.*#*
This procedure describes the responsibilities and mechanisms used to perform all maintenance activities under the control of the Superintendent, Maintenance.
2.0 APPLICABILITY This procedure applies to all personnel participating in or responsible for maintenance activities under the control of the Superintendent of Maintenance.
Specifically excluded are modification activities which are addressed in Procedure G-9 and instrument and control system activities which are addressed in (3
the RP series procedures.
c) 3.0 GENERAL REQUIREMENTS 3.1 All Safety-Related maintenance work must be performed according to documented instructions, procedures, or drawings of a type appropriate to the circumstances.
3.2 Records shall be maintained to provide objective evidence and veri fy that the plant has been maintained in accordance with required specifications.
Maintenance records for Safety-Related systems or components must contain at least the following:
3.2.1 A
reference to the Instructions, Procedures, and/or Drawings used.
3.2.2 The plant equipment number, equipment description, or the system number, as applicable.
3.2.3 A list of any calibrated tools or equipment used, and calibration date.
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FORM (B)372 22 3642 Laiw=W
P-12 Issue 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 11
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SerVlCe*
PUBUC SERVICE COMPANY OF COLORADO
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3.2.5 A description of the as found, as left condition, and the work performed.
3.2.6 A list of replacement parts used, and/or material used, and a copy of the Direct Charge Stores Requisition or a reference to it.
3.2.7 The signature of the person assigning the work.
3.2.8 The signature of the workman performing the work.
3.2.9 The signature of the QC Inspector.
3.2.10 The signature or stamp of the inspector which verifies the acceptability of work performed.
3.2.11 The date and length of time of work performance.
3.2.12 The signature of the supervisor reviewing the report.
3.2.13 Signature or stamp of the QC Inspector indicating the acceptance of any testing performed and the results of those tests.
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3.2.14 A record of dimensions, tolerances, or parameters v
when appropriate.
3.2.15 Selected records, as identified in Procedure Q-17, are forwarded to the Records Center.
3.3 Any work to be performed which could affect plant operations must be authorized by the Shift Supervisor.
3.4 Equipment clearances shall be obtained in accordance with Procedure P-2.
3.5 Work that involves radioactive or contaminated waste and radiation or contamination areas shall be performed in accordance with Procedure P-3.
3.6 Under off-normal conditions when normal supervision is unavailable, the Shift Supervisor acts for the Scheduling representative and/or the appropriate supervisor as necessary. This does not apply to work stop situations.
See Section 4.13.
3.7 All replacement parts and materials used in Safety-Related systems or components are obtained and issued as described in Procedure P-5.
O FoRMICl372 22-3643
P-12 Issue 1
/% Pub llC FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 11 SerVlC9" PUBUC SERVICE COMPANY OF COLORADO m
i 3.8 Consumables such as oil, grease, distilled water, insulation varnishes, cleaning solutions, etc.,
used in connection with maintenance activities are purchased, identified, and controlled in accordance with Procedure P-5.
3.9 Cleanliness of fluid systems, piping, and components undergoing maintenance activities shall be maintained in accordance with the applicable requirements and acceptance criteria using STD-3 for guidance.
3.10 Maintenance programs and policies will be detailed in Maintenance Administrative Procedures (MAP).
3.11 All maintenance activities shall be controlled by a Station Service Request (SSR).
The SSR process is described in procedure P-7.
3.12 Maintenance records are periodically reviewed by the Plant Engineering Section to identify abnormal trends and equipment requiring abnormally frequent repairs.
Identified problems are referred to the responsible organization for action.
3.13 Maintenance procedure approvals and deviations shall be processed in accordance with procedure G-2.
Y 3.14 Maintenance activities which involve fire protection interface or use of combustible materials shall be controlled in accordance with Procedure P-8.
3.15 Maintenance activities shall be performed in such a manner to ensure safe work practices, housekeeping and cleanliness in accordance with Procedure P-10.
3.16 Maintenance documents are to be filled out using a ball point pen. Corrections to entries on these documents are to be made by a line out accompanied by initials of the person correcting the entry and the date of the correction.
The original entry should be left legible.
White out is not to be used.
3.17 Maintenance procedure generic format will be in accordance with Procedure G-2's general format.
Specific format, unique to Maintenance will be in accordance with a Maintenance Administrative Procedure.
Ob FORM tCl 372 -22 3643
'P-12 Issue 1
PubllC FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 11 ServlCe*
PUBLIC SERVICE COMPANY OF COLORADO qQ 4.0 PROCEDURE 4.1 The Station Manager is responsible for all maintenance activities.
4.2 The Superintendent, Maintenance is responsible for implementation of this procedure. He is also responsible for determining those activities that do not require an SSR.
4.3 The Superintendent of Technical Services Engineering is responsible for providing maintenance engineering services and for preparing, periodic review, and technical input to the maintenance procedures.
4.4 A
QC Supervisor is responsible for determining QC inspection requirements.
4.5 The Maintenance Supervisor (s) is responsible for:
- 1) ensuring that the Maintenance Personnel and contract personnel performing work within the scope of this procedure as defined in Section 2.0 conduct all activities in accordance with this procedure; 2) for ensuring that personnel are faniliar with the requirements and processes
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of the Maintenance Procedures for the work they are fa performing; 3) specifying which sections of a procedure V
are to be used if the entire procedure does not apply.
4.6 All personnel performing maintenance activities within the scope of this procedure are responsible for the following:
4.6.1 Work shall be authorized by a Station Service Request (SSR) in accordance with Procedure P-7, except as authorized by the Shift Supervisor for emergency maintenance or by the Superintendent, Maintenance.
4.6.2 Work shall be performed in accordance with an approved procedure when one exists or in accordance with Supervisors' written instructions on the SSR when an approved procedure does not exist.
Procedure deviations shall be authorized per Procedure G-2.
SSR work descriptions shall be changed in accordance with Procedure P-7.
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FORM (C)372 22 3643
P-12 Issue 1
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 11
$9fVIC9" PUBUC SERVICE COMPANY OF COLORADO nC 4.6.3 Quality Control witness and hold points shall not be violated. (QC witness and hold points are defined in ProcedureG-1.) QC will typically be notified of the starting of work during routine planning meetings on safety related SSR's;
- however, the workman is responsible for notification of QC for hold and witness points.
Quality Control witness and hold points may be altered in any MP for a specific SSR (i.e., work activity) by the QC Supervisor or his designee without issuing a Procedure Deviation Request.
The basis for this is that the assignment of QC verification points does not affect the technical content nor the intent of the procedure.
4.7 When a witness or hold point is encountered in a procedure, work shall be stopped and QC notified by the workman. Work will be performed as follows:
For a hold point, a QC Inspector shall be present during the performance of the step. After the step is completed, the workman and QC Inspector shall sign that the step was performed or the inspection was completed.
For a witness point, a QC Inspector may or may not be (m
present during the performance of the step.
A witness h
point may be postponed verbally. Step completion shall be documented as for a hold point.
If a witness point is postponed, the workman shall document the postponement, on the procedure, at the witness point identifying the QC Supervisor or QC Inspector who authorized postponement, prior to performance of the step. The workman will notify QC when the work is complete.
A witness point may be postponed only by a QC Supervisor or QC Inspector.
4.8 Maintenance within the scope of this procedure shall be divided into two catagories, Preventive Maintenance and Corrective Maintenance.
Preventive Maintenance (PM) activities are those that are performed at preplanned intervals without knowledge of an equipment deficiency and are intended to sustain equipment in the best possible repair to aid in efficiency and provide for satisfactory performance of designed functions.
Corrective Maintenance (CM) activities are those that are performed on equipment and components with known deficiencies and is intended to restore equipment to O
minimum design requirements.
FORM (C)372 22-3643
P-12 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION
'Page 6 of 11
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$9FVIC9" PUBUC SERVICE COMPANY OF COLORADO Procedures for PM activities and CM activities will be in the same format and in some cases the same procedure will be used for both.
4.9 The SSR is the authorizing document for performance of work. As such, it will define the following:
4.9.1 The task to be performed, and the specific component (s).
4.9.2 The scope of work; the maintenance procedure or procedure sections, by number, to be used.
If specific sections are not identified, the entire maintenance procedure is to be used.
A POR must be written if a change is needed on any step required by the SSR.
A PDR is not needed when the SSR identifies specific sections and not the entire procedure, for work.
4.9.3 The requirement for QC inspection.
4.9.4 The QC, component and plant testing requirements
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necessary to put the component (s) back in service
's and declare it operable.
4.9.5 Special documents such as NCRs, ARs, etc.
The detailed data to be entered is described in Procedure P-7.
4.10 The following is an outline of the basic process for performing either Preventive or Corrective Maintenance activities.
4.10.1 The need for a PM or CM action has been identified, by the PM interval, Action Request, NCR or other mechanism.
4.10.2 An SSR is generated.
4.10.3 The SSR is evaluated and a work package is put together that may
- include, as necessary, procedure (s), drawing (s), NCR(s), list of parts, purchase order (s), etc.
4.10.4 The SSR is reviewed by QC to determine if QC is
- required, t'~'
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FORM (C)372 22 3643
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P-12 Issue 1
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Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 7 of 11 PUBUC SERVICE COMPANY OF COLORADO 4.10.5 The manpower requirement is determined and the work is scheduled based on the urgency of the activity and plant conditions.
4.10.6 The appropriate Maintenance Supervisor assigns personnel to the task (s).
4.10.7 The Shift Supervisor determines the actual start time of the activity based on plant conditions, clearances, plant safety, etc., where appropriate.
4.10.8 The workman, notifying QC based on requirements of the SSR, completes the task specified in the SSR and informs the Maintenance Supervisor.
4.10.9 The Maintenance Supervisor ensures the maintenance documentation is completed.
4.10.10 The Shift Supervisor has the required testing conducted.
4.10.11 The SSR is closed and the work package is assembled, reviewed, approved and forwarded for document storage.
(d' In the event that testing in 4.10.10 indicates that further maintenance activity is necessary, a new SSR shall be generated and the process is repeated.
In the event that plant operating conditions will delay required testing for an extended period of time, a new SSR may be generated for testing in accordance with procedure P-7, and the SSR work package may be closed referencing the new SSR number and the testing is conducted when plant conditions permit. The previous SSR is closed out by ensuring that a new SSR is generated using the suffix entry (item 39, SSR form, Procedure P-7) and the new SSR number is included in work done entry (item 73, SSR form, Procedure P-7).
4.11 Maintenance procedures shall be approved by the Superintendent, Maintenance or his designee in accordance with Procedure G-2.
4.12 When, during the process of performing a maintenance activity, a nonconforming condition is thought to exist, the following actions shall be taken:
4.12.1 The component / equipment will be placed in a condition that will not damage the component nor produce a personnel hazard.
bv FORM (C)372 22 3643 i
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[p PubllC FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 of 11 W Service ~
pusuc senvice company or cotonaoo V('3 4.12.2 The work activity will stop on the safety related portion of the activity affected by the non-conforming condition.
4.12.3 The following personnel will be notified:
The Shift Supervisor The appropriate Maintenance Supervisor The QC Supervisor 4.12.4 The workman should make an entry in the Work Reporting Data Section of the SSR, including date and time, that describes the reason for the work stop.
4.12.5 A review of the potential nonconforming condition will be conducted to determine if a nonconforming condition exists.
If it does, an NCR will be generated.
If it does not, the appropriate Maintenance Supervisor will authorize resumption of work. An entry on the SSR following the entry in 4.12.4, will explain the basis for work resumption.
In either case, work on the specific component p,
thought to be nonconforming will not resume until Q
authorized by the appropriate Maintenance Supervisor and documented by the entry on the SSR, or upon receipt of a dispositioned NCR.
4.12.6 Parallel work on the main component or remaining equipment may continue, if in the opinion of the Maintenance Supervisor and the QC Inspector, it will not affect nor be affected by the nonconformance.
For
- example, if a Safety-Related valve and operator are being disassembled for inspection and an indication of a nonconformance is found on the valve stem, disassembly of the valve and operator may continue and inspection and reassembly performed. The valve stem, however, may not be worked nor reinstalled until the possible nonconforming condition is evaluated.
If an NCR results from the evaluation, the restrictions of Q-15 apply.
FORM (C)372 22 3643
P-12 Issue 1 O SGIVice*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 9 of 11 PUBUC SERVICE COMPANY OF COLORADO V
4.13 When work is stopped or not allowed to start, the appropriate Maintenance Supervisor or Superintendent, Maintenance and the QC Supervisor will be notified immediately. The Maintenance Supervisor will notify the Shift Supervisor if it appears that the problem will not be readily resolved and the stop work will be lengthy.
4.14 The maintenance procedures will identify calibrated tools and consumables. The term "or equivalent" will allow for substitution of these items. To ensure that equivalents are, in fact used, an Equivalent List, MAP-20, will be generated and maintained. When an equivalent is used, it will be documented on the SSR, in the Work Reporting Data Section.
4.15 Maintenance Procedures to address special processes (i.e.,
welding, heat treating, etc.) will not necessarily be included in the maintenance procedure program as outlined in MAP-11. Control of special processes shall be in accordance with Procedure Q-9.
Reviews and approvals of these special procedures shall be required to ensure that the work performed is in accordance with the required specifications.
4.16 Procedures provided by equipment suppliers shall be
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processed and formatted in accordance with a Maintenance V
Admistrative Procedure (MAP) or included in the work description of an SSR at the discretion of the Superintendent, Maintenance.
4.17 Maintenance procedures shall be written in a format that is consistent with logical work sequencing.
The identification mechanism for steps that do not require specific sequencing will be detailed in MAP-11.
4.18 Testing requirements that are within the scope of the specific work defined in the maintenance procedure, shall be included in the maintenance procedure. An example of this type of testing would be meggering of electrical components.
4.19 Manufacturers data such as drawings, manuals and specifications which update current information may be obtained by the Maintenance Department directly from the manufacturer. Upon receipt of such data, the Maintenance Department will transmit it to the Nuclear Engineering Division (NED) - Denver and submit an Action Request (GSAR),
in accordance with the Procedure G-3 to have the data issued in accordance with Procedure G-10.
4.20 Post Maintenance test requirements shall be identified in
/^i the Maintenance Procedure.
V FORM tC)372 22 3643
P-12 Issue 1 0 Service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 10 of 11 PUB'.lC SERVICE COMPANY OF COLORADO l\\
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5.0 REFERENCES
5.1 Procedure G-1, " Glossary of Abbreviations and Definitions" 5.2 Procedure G-2, "FSV Procedure Systems" 5.3 Procedure G-3,
" Action Request
- Preparation and Processing" 5.4 Procedure G-9, " Controlled Work Procedures" 5.5 Procedure G-10, " Data Management" 5.6 Procedure P-2,
" Equipment Clearances and Operations Deviations" 5.7 Procedure P-3,
" Radioactive / Contaminated Waste / Area Control" 5.8 Procedure P-5, " Material Control" 5.9 Procedure P-7, " Station Service Request Processing" 5.10 Procedure P-8, " Fire Fighting and Prevention" (g) 5.11 Procedure P-10, " Safe Work Practices" v
5.12 Procedure Q-9, " Control of Special Processes" 5.13 Procedure Q-11, " Test Control" 5.14 Procedure Q-15, " Control of Nonconforming Items" 5.15 Procedure Q-17, "FSV Station Vital Records" 5.16 SMAP-21, " Post Maintenance Testing" 5.17 MAP, " Maintenance Administrative Procedures" 6.0 ATTACHMENTS None
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v FORMICl372 22 3643
I P-12
' Issue 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 11 0 service
- PUBLIC SERVICE COMPANY OF COLORADO
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7.0 COMMITMENTS The step (s) and section(s) listed below may not be deleted without issuance of comparable controls. The procedure itself, if initiated as a result of commitment corrective action, may not be deleted without issuance of comparable controls.
7.1 This procedure is a result of commitments made to the NRC in P-85107.
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FORM (C)372-22 3643
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Page 1 of 3 0 ServlCe*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION PUBUC SERVICE COMPANY OF COLORADO 7/15/85 O
FSV ADMINISTRATIVE PROCEDURES ISSUE EFFECTIVE NO.
SUBJECT NUMBER DATE G-0 DELETED 06-06-84 G-1 DEFINITIONS AND ABBREVIATIONS 13 11-05-84 G-2 FSV PROCEDURE SYSTEMS 17 06-28-85 G-3 ACTION REQUEST-PREP. & PROCESSING 6
10-16-84 G-4 SECURITY AND VISITOR CONTROL 14 05-29-85 G-5 PERSONNEL EMERGENCY RESPONSE 17 06-07-85 G-6 CONTROL OF SPECIAL NUCLEAR MATERIAL 3
10-09-81 G-7 FSV PROJECT TRAINING AND 13 03-21-85 x
QUALIFICATION PROGRAMS s
G-8 COMPLIANCE WITH 10CFR21 5
10-26-84 REQUIREMENTS G-9 CONTROLLED WORK PROCEDURES 6
12-05-84 G-10 DATA MANAGEMENT 5
03-20-84 G-11 UNCLASSIFIED SAFEGUARDS INFORMATION 5
04-29-85 G-12 CLASSIFIED DOCUMENTS 3
10-19-84 G-13 FITNESS FOR DUTY 1
02-04-85 P-1 PLANT OPERATIONS 12 09-13-84 P-2 EQUIPMENT CLEARANCES AND SYSTEM 12 11-21-84 DEVIATIONS P-3 RADI0 ACTIVE / CONTAMINATED WASTE / AREA 10 05-01-85 CONTROL P-4 DELETED 07-27-83 P-5 MATERIAL CONTROL 8
05-24-84 O
P-6 DELETED 08-27-82 FORM (C)372 22 3643
Page 2 of 3 0 service Public FORT ST. VRAIN NUCLEAR GENERATING STATION PUBUC SERVICE COMPANY OF COLORADO 7/15/85
. /7 V
FSV ADMINISTRATIVE PROCEDURES ISSUE EFFECTIVE NO.
SUBJECT NUMBER DATE i
P-7 WORK CONTROL-SSR PROCESSING 10 03-21-85 P-8 FIRE PREVENTION AND FIGHTING 12 12-05-84 P-9 DELETED 06-05-81 P-10 SAFE WORK PRACTICES 5
10-01-84 P-11 RECORDING OF PLANT TRANSIENTS WHICH MAY BE CONSIDERED OPERATING CYCLES 1
05-14-82 Q-0 QUALITY POLICY 2
08-04-80 Q-1 FSV ORGANIZATION & RESPONSIBILITIES 6
03-21-85 Q-2 QUALITY ASSURANCE PROGRAM 3
08-31-83 Q-3.
DESIGN CONTROL 8
10-16-84 Q-4 PROCUREMENT DOCUMENT CONTROL 6
05-07-84 Q-5 INSTRUC., PROCEDURES AND DRAWINGS 3
08-31-83 Q-6 DOCUMENT CONTROL 4
12-21-84 l
Q-7 CONTROL OF PROCURED ITEMS 7
07-15-85 Q-8 IDENTIFICATION & CONTROL OF 4
02-22-84 MATERIALS, PARTS AND COMPONENTS Q-9 CONTROL OF SPECIAL PROCESS 7
02-04-85 Q-10 INSPECTION 6
01-11-85 l
Q-11 TEST CONTROL 4
07-15-85 Q-12 CONTROL OF MEASURING EQUIPMENT 4
03-17-82 Q-13 HANDLING, STORAGE, AND SHIPPING 5
02-21-85 Q-14 INSPEC., TEST AND OPERATING STATUS 3
08-31-83 Q-15 CONTROL OF NONCONFORMING ITEMS 4
07-08-85 FORMICl372 22 3643
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FSV ADMINISTRATIVE PROCEDURES ISSUE EFFECTIVE NO.
SUBJECT NUMBER DATE l
Q-16 CORRECTIVE ACTION SYSTEM 6
07-15-85 Q-17 FSV STATION VITAL RECORDS 7
05-17-85 Q-18 QA AUDIT AND MONITORING PROGRAM 8
11-05-84 O
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FORMIC 1372 22 3843