ML20138J138
| ML20138J138 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/03/1985 |
| From: | Biddle R, Will Smith GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20138J109 | List: |
| References | |
| 116, NUDOCS 8510290263 | |
| Download: ML20138J138 (51) | |
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$ ~ Number Nuclear OYSTER CREEK NUCLEAR GENERATING STATION PROCEDURE 116 Title Revision No.
Surveillance Test Program 16 Applicability / Scope Regons{bl fg g Applies to work at Oyster Creek 2200 This document is important to safety El Yes O No Effective Date (09/23/85) 10/03/85 List of Effective Pages Page Revision Page Revision Page Revision 1.0 16 E3-1 14 E5-18 16 2.0 14 E4-1 14 E5-19 16 3.0 16 ES-1 16 E5-20 16 E5-2 16 E5-21 16 4.0 14 5.0 14 ES-3 16 ES-22 16 6.0 14 E5-4 16 E5-23 16 7.0 14 ES-5 16 E5-24 16 8.0 14 E5-6 16 E5-25 16 ES-7 16 ES-26 16 9.0 14 10.0 14 E5-8 16 ES-27 16 11.0 14 E5-9 16 E5-28 16 12.0 15 ES-10 16 E5-29 16 13.0 15 E5-11 16 E5-30 16 14.0 15 E5-12 16 15.0 14 E5-13 16 16.0 14 E5-14 16 17.0 14 E5-15 16 El-1 E5-16 16 NON CONTROLLtv E2-1 16 13 E5-17 16 This M ""*' #
- Ee Kept Ul1 N OM6 bcq (3ydthr C'h4 Signature Concurring Organization Element Date Originator bfB - a TLANT- EN6/MEEhJM6 9//3/85 Concurred by ghj P E%MM DMN N PRG Chairman f//f/($~
1 bv Mgr. OC QA MOD / OPS hQ->
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E Approved by
[h Nd Vice President and Director. 0.C. f[MF A'OOO10'51 2 84 8510290263 851022 1.0 PDR ADOCK 05000219 PDR P
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OYSTER CREEK NUCLEAR GENERATING NUCIGar STATION PROCEDURE 116 litle Revision No.
14 Surveillance Test Program l.0 PURPOSE 1.1 This procedure establishes the requirements and defines the responsibilities for the preparation, review, approval and revision of Surveillance Test Schedules.
1.2 This procedure establishes the requirements and defines the responsibilities for the peformance and review of Surveillance Tests.
1.3 This procedure is not applicable to the In-service Inspection requirements (Section 4.3.8/ Table 4.5.1 of the Technical Specifications) or the Environmental Technical Specifications (Appendix B).
The Manager - Special Processes and Programs is responsible for ISI program requirements per Reference 2.7 and the Manager - Environmental Controls is responsible for the Environmental Monitoring Program per Reference 2.8.
2.0 REFERENCES
2.1 Oyster Creek Nuclear Generating Station Operating License and Technical Specifications.
2.2 Procedure 107, " Procedure Control" 2.3 Procedure 104, " Control of Nonconformance and Corrective Action."
5 2.4 Procedure 125.1, "In-service Testing Program Administration."
7 2.5 GPU Nuclear Operational Quality Assurance Plan.
5 3 2.6 Procedure 832.1, " Chemistry Surveillance Test Program" 2.7 6150 ADM-3272.01 Special Processes and Programs ISI Program h Development and Implementation i
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Nwnk OYSTER CREEX NUCLEAR GENERATING NUCI68r STATION PRCCEDURE 116 Title Revision No.
Surveillance Test Program 16 2.8 Procedure 101.10. " Responsibility for Oyster Creek Environmental Program Implementation Review and Audit" 2.9 Procedure 118, " Preventive Maintenance Administrative Procedure" 3.0 RESPONSIBILITIES 3.1 Supervisor - Operations Engineering:
3.1.1 Ensuring that Surveillance Test Schedules are developed and revised in accordance with Sections 4.1 and 4.2.
3.1.2 Auditing the surveillance-related activities assigned to plant departments against the Master Surveillance Test Schedule and the Refueling Outage Surveillance Test Schedule.
3.1.3 Ensuring that the Master Surveillance Schedule and Refueling Outage Surveillance Schedule are updated to reflect Technical Specification changes, other surveillance-related commitment:, or changes to test i
frequencies due to results of trending.
3.1.4 Ensuring that a cross-reference document is maintained i current to designate the Surveillance Procedure used to 1
meet the Surveillance Test requirements of Reference 2.1, (refer to Attachment 1).
g 3.1.5 Ensuring that Surveillance Test Procedures are developed 5 and revised as necessary to meet the requirements of I b l s Reference 2.1, 2.5 and other commitments.
l 2 3.1.6 Trending and analysis of In-service Test Program data in l
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$ accordance with Reference 2.4.
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s Number NUINI OYSTER CREEK NUCLEAR GENERATING STATION PROCEDURE 116 Title Revision No.
Surveillance Test Program 14 3.1.7 Reviewing and routing procedures in accordance with Step 5.6.
3.1.8 Auditing completed Surveillance Test documentation to ensure compliance with the Master Surveillance Schedules or Refueling Outage Surveillance Test Schedule and with the maximum allowable surveill,ance intarvals allowed by Section 1.0 of Reference 2.1.
3.1.9 Notifying the Manager - Operations Engineering and responsible Department Manager of any missing Surveillance Tests. This is an audit function intended to identify any missed surveillance.
3.1.10 Reviewing and signing " Surveillance Test Omission Forms" to verify omission is acceptable per Reference 2.1.
3.2 The Supervisor I & C Engineering is responsible for the following:
3.2.1 Ensuring that a cross-reference document is developed and maintained current to specify the document file number to be used for each Surveillance Procedure. '
3.3 Hanager Plant Operations, Operational Maintenance, PM and l Surveillance Manager, Core Manager, Manager Plant Chemistry and 5 Radiological Controls Manager:
3.3.1 Ensuring that surveillance-related activities assigned to 5
,their departments are performed in accordance with the l Master Survelliance Test Schedule and Refueling Outage Surveillance Test Schedule.
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' ' Number NUCIGar OYSTER CREEK NUCLEAR GENERATING STATION PROCEDURE 116
- Revision No.
14 Surveillance Test Program 3.3.2 Ensuring that surveillance-related activities are conducted in accordance with Steps 3.8. 5.1, 5.2 and 5.5 of this procedure. Chemistry surveillance-related activities will be conducted in accordance with Steps 3.8,
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4.3 and 5.7 of this procedure.
3.3.3 Notifying the Supervisor - Operations Engineering of any missing Surveillance Test results. This is an audit function intended to identify any missing Surveillance Tests.
3.3.4 Determining when scheduled Surveillance Tests may be
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~ omitted, completing a " Surveillance Test Omission Form" (Figure 116-3) and forwarding it to the Supervisor -
Operations Engineering. The "Omtssion Form" should be submitted on or before the scheduled date.
3.3.5 Ensuring that Surveillance Tests that are not performed due to plant conditions or when systems are allowed to be inoperable, in accordance with Reference 2.1, are rescheduled for performance when plant conditions permit or pri v to startup following outage.
3.3.6 Ensuring that when Technical Specification-related E Surveillance Tests are not performed on the exact date and shift specified in the Master Surveillance Schedule that
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o E the following criteria are reviewed for compliance. If 3
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- Number Nuclear OYSTER CREEK NUCLEAR GENERATING STAT 1ON eROCEouRE ii6 Title Revision No.
Surveillance Test Program 14 such compliance is not met, a Deviation Report shall be submitted per the requirements of Procedure 104, Reference 2.3.
3.3.6.1 Surveillance Tests shall be performed within.the specified Technical Specification time interval with a maximum allowable extension not to exceed 25 percent of the surveillance interval.
3.3.6.2 Surveillance Tests shall be performed within the specified Technical Specification time interval with a total maximum combined inter' val time for any 3 consecutive surveillance intervals, not to exceed 3.25 times the specified surveillance interval.
3.3.7 Ensuring Refueling Outage Surveillances are preplann'ed and interfaced with che particular maintenance tasks of each Refueling Outage to assure data accuracy and the minimization of reportable occurrences.
3.3.8 Assuring the Refueling Outage Surveillance Test Schedule reflects Departmental Refueling Outage interfacing and preplanning with regard to tests which are to be done more 5 than once during the Outage.
5 NOTE: The Operational, Maintenance, PM and 5
3 Survelliance Manager shall be responsible for overall PM program management which includes the
! maintenance and review of equipment history i
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Number Nuclear OYSTER CREEK NUCLEAR GENERATING -
STATroN eRoCEouRE iis Title Revision No.
Surveillance Test Program 14 1
records per Refe'rence 2.9, Preventive Maintenance Administrative Procedure.
3.4 Group Shift Supervisor:
3.4.1 Remaining fully aware of the status df all plant systems during and after Surveillance Testing.
3.4.2 Re"lewing Surveillance Test Procedures in accordar.ce with Steps 3.8 and 5.3.
3.4.3 Ensure that action required by Reference 2.3 has been initiated to correct identified discrepancies.
3.5 Responsible Group Supervisor:
3.5.1 Thoroughly review the test documentation in accordance with Steps 3.8 and 5.2.
3.5.2 Ensuring that tests are planned and executed so as to minimize the time that systems or components are out-of-service (i.e. tests should be completed and equipmentreturnedtonormal,wherep55sible,during breaks and shift turnover or testing should continue uninterrupted.)
NOTE: Technical Specifications Table 3.1.1 limits out of service times for instruments to one hour per 5 month to conduct tests and calibrations.
I 3.5.3 _ Ensuring the following is performed for surveillances that 3 result in Technical Specification instrument sensors (Reference 2.1, Table 3.1.1) being removed from service:
a.
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Nurnw Nuclear OYSTER CREEK NUCLEAR GENERATING STATION PROCEDURE 116 Revision No.
Surveillance Test Program 14 3.5.3.1 The cumulative out of service time for the previcus 31 days for each sensor to be tested has been obtained and recorded on the Equipment .
Out of Service Sheet (Figure 116-4) and attached to the surveillance procedure.
3.5.3.2 Obtain GSS signature on Figure 116-4 prior to start of testing.
3.5.3.3 If any sensor with an out of service time of >
30 minutes, of if it is believed that the sensor test / calibration cannot be completed within the remaining out of service time allowed, the test shall be reviewed prior to performance with Plant Operations and Plant Engineering as necessary to ensure the Technical Specification r9quirements are met.
3.5.4 Designating one person who will be responsible for performance / coordination of the test and documentation in l
accordance with Step 5.1.
3.6 Person designated as responsible for performing the Surveillance Test:
3_. 3.6.1 Performing or coordinating the performance of the test in 2 accordance with the approved procedure.
3 5 3.6.2 Documenting test data and results in accordance with the
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% test procedure, Steps 4.3 and 5.1 of this procedure. .
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Ncmber Nuclear OYSTER CREEK NUCLEAR GENERATING 116 STATION PROCEDURE
- Revision No.
14 Surveillance Test Program 3.7 The Supervisor-Licensing:
3.7.1 Notifying the Manager Plant Engineering of any .
surveillance-related Technical Specification Amendments within twenty-four (24) hours of receipt.
3.8 All individuals reviewing Surveillance Test documentation:
3.8.1 Reporting any previously unrecognized deviations from procedure acceptance criteria, to the Group Shift Supervisor.
3.8.2 Returning, via the normal chain of command, any test documentation not in accordance with Step 4.3 below to the Group Supervisor of the person performing the test for disposition or corrective action.
3.8.3 Documenting, in the Comments" section of the
" Surveillance Review Form", any action taken in response to identified discrepancies by describing it or referencing further informatto.1 4.0 REQUIREMENTS 4.1 The following types of schedules will be developed to reflect Survelliance Test commitments made in various documents. Such documents would include the Oyster Creek Technical Specifications and letters between GPUN and the United States Nuclear Regulatory f=
Commtssion.
These schedules may also include Surveillance Tests which are not fs required by any such commitments, but are regularly performed and
- conveniently included. However, the documentation and review of
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^ Number l Nuclear OYSTER CREEK NUCLEAR GENERATING ;
STa110N ea0CEDuaE iis M' Revision No.
14 Surveillance Test Program any tests included in these schedules must meet the requirements of this procedure. Surveillance Tests which are not required to meet commitments or regulatory requirements may be omitted from ,
these schedules at the discretion of the responsible Department Manager.
4.1.1 A Master Surveillance Test Schedule, which delineates all Surveillance Test requirements, shall be developed on a yearly basis. This schedule shall normally be developed by an engineer assigned to the Plant Engineering Department and approved by the Manager Operations Engineering.
4.1.2 Prior to each ueling outage a Refueling Outage Surveillance Test Schedule, delineating the special Surveillance Test requirements related to the outage, shall be developed. These schedules shall normally be prepared by an engineer assigned to the Plant Engineering Department and approved by the Manager Operations Engineering.
4.2 Revisions to Master and Refueling Outage Surveillance Test Schedules require the approval of the Manager Operations E Engineering.
? 4.3 Requirements for Surveillance Test documentation:
5 3 4.3.1 Surveillance Test documentation shall be legible. All entries should be written in black ink.
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Number Nuclear OYSTER CREEK NUCLEAR GENERATING STATION PROCEDURE 116 Title Revision No.
Surveillance Test Program 14 4.3.2 All blanks should be filled in or an explanation given or referenced indicating why it was not. If the step was not applicable, it should be clearly indicated such as with "N/A" or "N/R".
4.3.3 Write-overs or erasures are not allowed for documentation on Surveillance Test. Mistakes shall be crossed out with a single line and initialed by the person performing the surveillance.
4.3.4 Numerical data required by the procedure will be recorded in the space provided.
4.3.5 Satisfactory completion of a procedural step 'w111 be _
documented with the initials of the person performing the step verification. No " check" marks or "x" marks are allowed to be used to document completion of a step.
4.3.6 If the step was not completed satisfactorily, an explanation should be given or referenced indicating why the step was not completed satisfactorily.
4.3.7 Review of Surveillance Test documentation will be documented with the signature, not initials of the reviewer, on the " Surveillance Review Form".
5 4.3.8 If test was performed on only a portion of the components required this should be noted in " Comments" section of g " Surveillance Review Form" and, if performed after maintenance, the Job Order number that work was performed
! under should be listed on the " Surveillance Review Form".
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OYSTER CREEK NUCLEAR GENERATING YUCl68r STATION PROCEDURE 116 Revision No.
Title Surveillance Test Program 15 4.3.9 Procedure changes shall be incorporated in accordance with Reference 2.2.
4.3.10 Data which does not meet acceptance criteria or indicates some other deviation from satisfactory performance should be clearly indicated such as circled with a contrasting color, with an asterisk or with a note in the " Comments" section.
4.3.11 If documentation of an action is required, the necessary data shall be recorded as the task is performed.
5.0 Responsibilities for performance and review of Surveillance Test Procedures (refer to Figure 116-2).
5.1 The person designated as responsible for performing the Surveillance Test will:
5.1.1 Perform or coordinate the performance of the test in accordance with the approved procedure. Procedure steps shall be performed in the as written sequence unless otherwise specified in the procedure.
Test performance should be planned and executed in a manner that will minimize the tine that a system or component is out-of-service without deviating from the as g written sequence.
l [ 5.1.2 Document test data and results in accordance with the test l ! procedure and Step 4.3 of this procedure.
l 2 g 5.1.3 Ensure any electrical junction boxes, panels or l l Instrumentation enclosures opened during the performance of the surveillance, have been properly closed; ensure any ACOO105011 82 12.0
Nuclear OYSTER CREEK NUCLEAR GENERATING STATION PROCEDURE 116 Title Revision No.
Surveillance Test Program 15 appitcable seal material is present and in good condition, and document this verification with his ;ignature on the
" Surveillance Review Form".
5.1.4 Fill out the heading and Section 1 of a
" Surveillance Review Form" (Figure 116-1) and attach it to the test procedure.
5.1.4.1 Instrument Technicians ensure that instrument history cards are complete when applicable.
5.1.5 Ensure the names and initials of all individuals performing the surveillance are filled out on the
" Surveillance Review Form".
5.1.6 Immediately upon completion of testing, inform the Group Shift Supervisor of completion of testing, current equipment status, and any deviations noted.
5.1.7 Immediately upon completion of testing, obtain the Group Shift Supervisor's signature or initials on the Test Data Sheet, if required, and on the " Surveillance Review Form".
5.1.8 Forward the test documentation to the responsible Group Supervisor, or leave it with the Group Shif t Supervisor, as directed.
g NOTE: For data recording extending over more than one l
I k shif t (ex. MSIV 5 percent closure test or Tech Spec Log Sheet), only the person attaching the 1 5 g " Surveillance Review Form" need sign the form.
5.2 The responsible Group Supervisor will:
5.2.1 Thoroughly review the test documentation for completeness, Acc010601142 13.0
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Nuclear OYSTER CREEK NUCLEAR GENERATING STATION PROCEDURE 116 Revision No.
Title Surveillance Test Program 15 accuracy, and deviations from the test procedure acceptance criteria and the documentation standard of Step 4.3 of this procedure.
5.2.2 Identify and explain, as necessary, any deviations, ibnormalities or omissions in the test data.
5.2.3 Inform the Group Shift Supervisor of any previously unidentified discrepancy.
5.2.4 Document his review by filling out and signing the Group Supervisor portion of the " Surveillance Review Form".
5.2.5 Upon completion of his review, forward the test documentation to the responsible Department Manager.
5.3 The Group Shift Supervisor will:
5.3.1 Sign or initial the Test Data Sheet, if required.
5.3.2 Review all Surveillance Tests with identified deviations to evaluate their effect on the safe operation of the plant.
5.3.3 Initiate whatever corrective action he considers necessary in response to identified deviations. For example: emergency ,
maintenance, test of redundant system, etc.
5.3.4 Ensure acti.ons required by Reference 2.3 have been initiated to correct / report any deviation noted during testing. For g example: Job Order, Deviation Report, etc.
k 5.3.5 Fill out and sign the GSS portion of the " Surveillance Review l
Form" to signify his understanding of test completion,
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equipment status, and identified deviations and to document g
g his review of identified deviation.
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' Number Nuclear OYSTER CREEK NUCLEAR GENERATING STATION eROCEDUaE ii6
- Revision No.
14 Surveillance Test Program NOTE: A Surveillance Test will be considered complete for scheduling or other " clock" requirements when the GSS has completed this review and signed the " Surveillance Review Form".
5.3.6 Inform the Manager Plant Operations of any potential reportable occurrences or other significant problems.
5.3.7 Upon completion of his revtew, forward the test documentation:
- To the Operations Control Manager if.a deviation is noted.
- To the responsible Group Supervisor otherwise.
5.4 The Operations Control Manager will:
5.4.1 Review all Surveillance Tests with identified deviations to evaluate their effect on the safe operation of the plant.
5.4.2 Evaluate identified deviations to determine their l reportability per Reference 2.1 and inform the Safety Review Manager of reportable or safety-related deviations.
5.4.3 Document his review by filling out and signing the Operations Control Manager portion of the " Surveillance 5 Review Form".
5.4.4 Upon completion of his review, forward test documentation j to the responsible Group Supervisor.
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OYSTER CREEK NUCLEAR GENERATING Nuclear STATION PROCEDURE 116
- Revision No.
Surveillance Test Program 14 5.4.5 For identified deviations that require a Job Order, he will fill in Job Order number in " Comments" section of
" Surveillance Review Form" (Reference J.O. No.).
5.5 The responsible Department Manager, or designee, will:
5.5.1 Review test documentation completed by his department.
5.5.2 Document his review by filling out and signing the Department Manager portion of the " Surveillance Review Form".
5.5.3 Forward the test documentation to the Supervisor -
Operations Engineering upon completion of his review.
5.6 The Supervisor - Operations Engineering will: _
5.6.1 Route IST related procedures to the IST coordinator.
5.6.2 Review completed test documentation per Steps 3.2.2 and 3.8.
5.6.3 Document his review by filling out and signing the
" Supervisor - Operations Fagineering " section of the
" Surveillance Review Farm".
5.6.4 Forward completed test documentation to- the Document Center for filing.
5.7 The Manager Plant Chemistry will:
5 5.7.1 Ensure that all Surveillance Tests are performed in
? 'accordance with Reference ? 6.
5 5.8 The IST Coordinator will:
Review IST-related Tests and extract data for the IST l 5.8.1 h program records.
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OYSTER CREEK NUCLEAR GENERATING Number Nuclear STATION eRocEooRE iis Title -
Revision No.
Surveillance Test Program 14 5.8.2 Initial the " Surveillance Review Form" indicating data has been obtained.
5.8.3 Return Surveillance Tests to Supervisor - Operations Engineering.
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" l Nehr OYSTER CREEK NUCLEAR GENERATING STATION PROCEDURE 116 Revision No.
Title Surveillance Test Program 16 Fig. 116-1 SURVEILLANCE REVIEW FORM Title of Surveillance Procedure Number Scheduled Test Date (From Surveillance Schedule)
Documentation and review signatures (circle Yes, No, N/A; describe or reference any corrective action in comments):
Names and Initials of all
- 1. Person responsible for performing test: Individuals Performing Test No Yes a. Procedure completed in entirety?
No Yes b. Equipment / system returned to normal?
No Yes c. All-test acceptance criteria satisfied?
Yes No d. Any other deviations noted?
NA Yes e. Inst history cards complete?
NA Yes f. Form 116-4 completed?
Name Initials All enclosures verifled checked and reclosed per Procedure 116, Step 5.1.3 Sign /Date /
- 2. Group Shift Supervisor:
Yes No e. Possible Reportable Occurrence?
No Yes f. Equipment / system considered operable?
, Yes N/A g. Deviation Report submitted?
Yes N/A h. Short Form submitted? (Short Form No. )
l Informed of completion of testing equipment status, and any deviations noted.
Sign /Date/ Time / /
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! 3. Operations Control Manager (if 1.c. is No or 1.d. is Yes):
l Sign /Date /
- 4. Group Supervisor:
No Yes 1. Regularly scheduled test? If no, explain in comments.
Sign /Date /
l 5 5. Department Manager: Sign 5 Logged in Surveillance 5 6. Supervisor - Operations Engineering: Records
- Initials l E 7. IST Coordinator / / or NA I
l Initials Date Time h Comments:
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. *. l OYSTER CREEK NUCLEAR GENERATING rJumber Nuclear STATION PROCEDURE 116 Title Revision No.
Surveillance Test Program 13 Fig. 116-2 Surveillance Documentation Review Flow Chart Person Responsible for Performing Surveillance
- Group Shift ' (1)
Supervisor v
Deviation <
0perations Control Identified Yes Manacer
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No g sf
- Group f, Safety Supervisor Review Manager
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1 s/
/**
Department Manager
/ % h se l Supervisor IST <
/**
Operations ( (2) > Coordinator !
Engineering l g Document Center Correction of Test Documentation I
- Previously Unrecognized Deviation
! (1) Other Material per Ref. 2.3 .
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- (2) IST Surveillances A000105011 82 E2-1
Number Nuclear OYSTER CREEK NUCLEAR GENERATING STATION PROCEDURE 116 Title Revision No.
Surveillance Test Program 14 Fig. 116-3 Surveillance Test Omission Form Title of Surveillance Procedure Number Scheduled Test Date (From Surveillance Schedule)
Reason for not performing test:
Plans for completing surveillance:
Department Manager /
Signature /Date Comments:
Logged in 5 Reviewed and noted by Surveillance Records
- Supervisor - Operations Engineering Signature Initials
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Number Nuclear OYSTER CREEK NUCLEAR GENERATING STATION PROCEDURE 116 Title Revision No.
Surveillance Test Program 14 Fig. 116-4 -
Equipment Out of Service Sheet To be filled out before performing surveillance.
Suveillance Title and Number This is to comply with Tech. Spec.(s) Table 3.1.1.
Component must not be out of service for more than 60 minutes in a 30 day period.
Information derived from history or Document Control Center.
I & C technicians will notify the Control Room when the sensor is valved out and back into service.
Signature and Date Time 0.0.S.
Amount of Out of Service Time Remaining for This Surveillance Component I.D. # Time for Previous 30 Days Surveillance Date 5
5 /
" Date
- Group Supervisor's Name 3
/
! GSS Date~
Notification prior to start of surveillance A000105011 82 E4-1
ATTACHMENT 1 Proc. 111 Rev. 16 CROSS EFEEllCE OF SUWEILLAllCE PROCEDUES Allo TE0lllICAL SPECIFICATI0llS -
1 NOTE: THIS CROSS REFERENCE HAS BEEN VERIFIED THROUGM TECHNICAL SPECIFICATION AMEN 0 MENT NO. 89 M KEY:
w SCHEDULE FREQUENCY i A - MSS 12-week cycle D - Daily B - MSS 3-year cycle W - Weekly 4 C - Startup/ Shutdown Schedule SM - Semi-monthly 0 - Refueling Schedule M - Monthly E - Tech Spec Log 0 - Quarterly R - Other S - Seat-annually Y - Yearly R - Refueling X - 1/18 Months 2 - 1/36 Months I
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ATTACHMCT 1 (Cont.) Proc. 115 Rev. 13 TABLE 4.1.1 MINIMUM CHECK. CALIBRATION & TEST ~
FREQUENCY FOR PROTECTIVE INSTRUMENTATION ACTUAL FRE0uENCY INSTRUMEllI CHANNEL CHECK / CALTIh8 ATE / T[11 CHECK / CALYasATE / TEST PMCEDugg SchED TESTING
- 1. High Reactor N/A 1/3 Mos. NOTE 1 N/A 1/3 Mos. 1/Mo. 619.3.017 A Scram Pressure 609.3.003 A Iso. Cond/ Rec Pp Trip 602.3.004 A g-
- 2. High Drywell N/A 1/3 Mos. NOTE 1 N/A 1/3 Mos. 1/Mo. 619.3.016 A Pressure (Scram)
- 3. Low Reactor Water 1/0 1/3 Mos. NOTE I 1/D(E) 1/3 Mos. 1/Mo. 619.3.013 A Level
- 4. Low-Low Water 1/D 1/3 Mos. NOTE 1.3 1/D(E) 1/3 Mos. 1/Mo. 610.3.010 A Core Spray / Logic not Reed.
Level 610.3.105 (SYS I) A Core Spray / Rec. Pp Trip 610.3.205 (SYS II) A
- 5. High Water Level N/A I/3 Mos. NOTE 1 N/A 1/3 Mos. 1/Mo. 619.3.011 A e in ! cram .
N Discharme Volte
- 6. Lew-Low-Low N/A 1/3 Mos. NOTE 1 N/A 1/3 Mos. 1/Mo. 619.3.006 A beater Level
- 7. High Flow in Main 1/D. 1/3 Mos. NOTE I 1/D(E) 1/3 Mos. 1/Mo. 619.3.005 A
'.teami t ne
- 8. Low Pressure in N/A 1/3 Mos. NOTE 1 N/A 1/3 Mos. 1/Mo. 619.3.007 Shutdown A Main Steamitne 619.3.000 Oper. A
- 9. Hish Drywell 1/D. i/3 Mos. NOTE 1 1/D(E) ------
1/Mo. 610.3.105 (SYS I) A Pressure (Core 610.3.205 (SYS II)
Cooitnet 1/3 Mos. &
- 10. Main Steam N/A N/A 1/3 Mos. N/A N/A Prior to 602.4.002 A&C Isolatton valve Startup fGrami NOTE 1: Initially once/ month, thereafter according to figure 4.1.1. with an interval not less than one month nor more than three months.
NOTE 2: At least daily during reactor power operatton, the reactor neutron flux peaktog factor shall be estimated and the flow-referenced APRM scram and rod block settings shall be adjusted tf necessary, as specified in Section 2.3. Spectf tcations (1) (a) and (2) (a).
NOTE 3: Use Procedure 610.3.010 when Core Spray Logic Testing is not required.
A = Master Surveillance schedule - 12 week cycle: - 8 = Master Surveillance Schedule - 3 Year Cycle; C = Startup. Shutdown Schedule:
Da Refueling Outage Requirements; E = Technical Spectftcations Log R = Other
ATTACHME2T I (Cont.) Proc. 116 Res. 16 TA8LE 4.1.1
_ ' MI;IMUM CHECK. CALIBRATION & TEST FREOuENCY Foe PROTECTIVE IMSTRUMENTATION ACTUAL FRE00ENCY , l
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INSTRUMENT CHANNEL CHECK / CAlfRSATE / T{$1 CHECK / CAlfRGATE / TEST PROCEDURE SCHEDULE
- 11. a. APRM Level N/A 1/3 D. N/A N/A 1/ Day N/A 1001.6
- 12. APHM Rod Blocks NOTE 2 1/3 Mos. 1/Mo. 1/D 1/wk 1/wk. 620.3.003 A 13.a.HighRadiatio$ 1/5 1/3 Mos. 1/wk 1/S(E) 1/3 Mos. 1/wk. 621.4.008 (Test) A on Main Steamitne 621.3.009 (Calth) A
- b. Sensors for N/A Each N/A N/A Each N/A 621.3.003 0 13 (a) Refueling Refueling g Outaae Outaae w
$ 14. High Radiation in Reactor Building
- a. Operating 1/S 1/3 Mos. 1/=k 1/S(E) 1/3 Mos. 1/wk. 621.3.005 (Calth) A floor 651.4.001 (Test)
- b. Ventilation 1/S 1/3 Mos. 1/wk 1/S(E) 1/3 Mos. 1/wk. 651.4.001 (Test) A Exhaust 621.3.005 (Calth)
- 15. High Radiation on 1/S 1/3 Mos. 1/wk 1/S(E) 1/wk. 1/wk. 621.4.007 (Test) A Ejector Off-Gas 621.3.002 (Calth)
- I/S Prior to 1/d . 620.4.005 A (Test)
Startup & (SF 26452) C & 0 (Calibration)
Shutdown
- 17. IRM Blocks N/A Prior to Prior to N/A Prior to Prior to 620.4.005 C and 0 Startup & Startup & Startup & Startup (SF 26852)
Shutdown - Shutdown Shutdown
- Calibration prior to startup and norinal shutdown and thereafter check 1/$ and test 1/wk untti no talger required.
Legend N/A = Not Appitcable; 1/S = Once per Shift 1 1/D = Once per Day; 1/3D = Once jper 3 Days; 1/bac = Once per week; 1/3 Mos. = Once every 3 Months
ATTACHMCT I (Cont.) Proc. 116 Rev. 13 . .
TABLE 4.1.1 MIZIMUM CHECK. CALIBRATION & TEST FREUuENCY FOR PEDTECTIVE INSTRUMENTATTON ACTUAL FRE0ur g ,
INSTRuPERI CHANNEL CHECK / CALIBRATE / TESI CliECK / CALIBg&IE / TESI PM)CEDURE SCHEDULL
- 18. Condenser Low N/A Each Each N/A Each Each 619.3.014 Refueling Refueling Refueling Refueling 619.3.015 0 Vacuum Outage Outage Outage Outage
- 19. Manual Scram N/A N/A 1/3 Mos. N/A N/A 1/3 Mos 619.4.012 A f, Buttons (Cks.
- 20. High Temperature N/A Each Each N/A Each Each 619.3.009 Sensor) D Main Steamitne Refueling Refueling Refueling Refueling 619.3.010 (Func.
Tunnel Outane Outane Outane Outmas Testl
- 21. SRM 1/S(F) Prior to 1/W . 620.4.004 A (Test)
Startup & C & D (Caltt-ration) ht%
- 22. Isolation Conden- N/A 1/3 Mos. 1/3 Mos N/A 1/3 Mos. 1/3 Mos 609.3.002 A ser High Flow m Delta P (Sta & Wt1 to
- 23. Turbine Trip N/A 1/3 Mos N/A N/A 1/3 Mos 619.4.002 A
[
- 24. Generation Load N/A 1/3 Mos. 1/3 Mos N/A I/3 Mos. T/3 Mos 619.3.00I ( 45%) A Rejection Scram 619.3.014 ( 40%)
- 25. Rectrculation N/A Each N/A N/A Each N/A 603.3.002 D Loop Flow Refueling Refueling Outane Outane
- 25. Low Reactor Pres- N/A 1/3 Mos. 1/3 Mos N/A 1/Mo. 1/Mo. 610.3.006 A sure Core Spray Valve Permissive
- 27. Scram Discharge Volume (Rod Block)
- a. Water Level High N/A Each 1/3Mos N/A 1/3 Mos. 1/Mo. 619.3.011 A Refueling Outage
- b. Scram Trip Bypass N/A N/A Each Re- N/A N/A Each Re- 656.4.001 0
. fueling fueling Outage Outage
- Calibration prior to startup and normal shutdown and thereafter check 1/5 and test 1/Wk untti no longer required.
Master Surveillance Schedule - 12 Week Cycle; B = Master Surveillance Schedule - 3 Year Cycle; C = Startup/ Shutdown Schedule A
E = Technical Spectrication Los: F = Reactor Log 0- Refueling Outage Requirements;
ATTACHMENT 1 (Cont.) Proc. 115 Rev. 15 . .
TABLE 4.1.1 MI.:'IPEM CHECK. CALIBRATION & TEST FREQUENCY FOR PROTECTIVE INSTRLatENTATION ACTUAL FREQUENCY .
INSTRLRtENT CHAMMEL N rK / CALIBRATE / TEST CHECK / CAtfas4TE / TESI PAGCEDURE SCHEDULE
- 28. Loss of Power
- 3. 4.16 KV Emergency Daily 1/18 Mos. I Mo. Daily 1/18 Mos. 1 Mo. Turb. Side. Tour Sheet (Check) -R aus Undervoltage 635.2.001 Data Sheet (Cal) D (Loss of Voltage) . Pke 31 & 32 g 612.2.882 (Test) A
- b. 4.16 KV Emergency Daily 1/18 Mos. 1 Mo. Daily 1/18 Mos. 1 Ho. Turb Bide. Tour Sheet (Check) R Bus undervoltage 635.2.001 Data Sheet (Cal) D (Degraded Voltage) Pks 31 & 32 632.2.002 (Test) A
- Calibration prior to startup and normal shutdown and thereafter check 1/S and test 1/2 until no longer required.
A = Master Surveillance Schedule - 12 Week Cycle; 8 = Master Survelliance Schedule - 3 Year Cycle: C = Startup/ Shutdown Schedule D = Refueling Outage Requirements: E = Technical 3pecification Los; F = Reactor Log
-E
>6.
I I
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ATTACHMC:T 1 (Cont.) Proc. 116 Rev. 13 TA8tE 4.1.2 APPL.
TRIF SYSTEM MINIttat TEST FREQUENCY ACTUAL TEST FREDUENCIES PMICEDuRE SClED TESTING
- 1. Dual Channel Same as for Respective Tested per Table 4.1.1 (Scram) Instrumentation in Table 4.1.1
- 2. Rod Black Same as for Respective Tested per Table 4.1.1 Instrianentation in Table 4.1.1 1
- 3. Containment Soray 1/3 Mos. 1/Mo. 607.3.002 A Each Trip System Each Refueling Outage Each Refueling Outage 607.3.002 D (Prior to Startup)
One at a Time
- 4. Automatic DegEgis- Each Refueling Outage Each Refueling Outage 602.3.005 D uration. Each Trip Systam. One at a time
- 5. tGIV Closure. Each Each Refueling Outage Each Refueling Outage 619.3.004 D (Loto Level)
Clisure Logic Circuit 621.3.003 (H1 Rad) independently 619.3.010 (Hi Temp)
(1 valve at a time) 619.3.005 (Mi flow) 619.3.007 (Low Press.)
M y 6. Core Sorav. Each Trip System. One at 1/3 Mos.
Each Refueltrg Outage 1/3 Mos.
Each Refueling Outage 610.3.005 610.3.005 A
D (Prior to Startup) cn a Time
- 7. Primary contain- Each Refueling Outage Each Refueling Outage 619.3.004 D (LoLo Level)
Olent Isolation. Each 619.3.003 (Mt DW Press.)
Cirsure Circuit 642.4.003 (RSCCW)
Independently f1 valve at a time)
- 8. Refuelina Inter- Prior to each Refueling Operations Prior to Refueling Operations and 656.4.001 D locks 1/4 . during Refueling C. Isolation Conden- Each Refueling Outage Each Refueling Outage 609.3.003 0 (Rx Hi Press) ser Actuation and 619.3.004 (LoLo Level) liglatien. Each Trip 609.3.002 (Isolation)
Circuit Independently (1 valve at a time) 610.3.010 Core Spray Logic Not Rec'd
- 10. Reactor Butidina Same as for Respective Tested per Table 4.1.1 619.3.003 R 11glation & SGTS Instrumentation in Table 4.1.1 619.3.004 R Initiation 651.4.001 W1y 621.3.005 A
- 11. Condenser Vacuum Prior to Each Startup Prior to Each Startup 630.3.002 C&D Isolation O'
ATTACMHCT I (Cant.) Proc. 116 Rev. 15 . .
4.2 REACTIVITY CONTROL APPLICABLE TECHNICAL SPECIFICATION REQUIREMENT ACTUAL TEST FernaarnarY 2ECEDURE(11 SCHEDULE 4.2.A. Demonstrate a 0.25% Delta K Shutdown Marsin following Each Refueling Outage 1001.26 D a refueling outage 1001.27 4.2.B. L e control rod drive housing support system shall Each Refueling Outage 717.1.005 .')
be inspected after reassembly 4.2.C.1. Scrant Insertion Times ( All Rods Following Each Refueling Outage (All Rods) 617.4.003 D Refueling)
- 3. Scram Insertion Times (8 Rods Each Outage) Prior to Each Start-up - 8 Rods 617.4.003 C Tested ps 4.2.D. Control Rod Exercising - Weekly 1/ Week 617.4.002 A Y
u 4.2.E. Survet11ance of the Standby Liquid Control System shall be as follows:
- 1. Pump Operabtitty - 1/Mo. 1/ Month 612.4.001 A
- 2. Baron Concentration Determination - 1/Mo. 1/ Month 823.7 (8) Chem. Monthly
- 3. Functional Test Ea. Refueling Outage Each Refueling Outage 612.4.002 D
- 4. Solution Volume and Temperature Check 1/ Day 1/ Day TS Log E 4.2.F. Reactivity Anomaly Check - Every EFPM 1/ Month 1901.17 A 4.2.G. SDV Vent and Drain valves
- 1. Verify Open 1/31 Days, except in Shutdown Mode
- I/ Shift C.R. Turnover N/A Sheet
- 2. Cycle fully quarterly 1/ Month 619.3.011 A
- Valves may be closed intermittently for testtog under administrative control.
ATTACHMENT I (Cont.) Proc. 115 Rev. 15 , .
4.2 REACTIVITY CONTE)L APPLICARLE i SCMEnutE TECHNICAL SPECIFICATION RE00IREMENT ACTUAL TEST FRE0uEMCY PMICEDUREfS1 4
4.2.H. Demonstrate all ldithdrawn Control Rods operable by demonstrating SDV Vent and Drain Valves operible. !
Once per Refueltog Cycle place Mode Switch in Shutdown and verify that:
- 1. Vent and Drain Valves Close in 60 seconds after At least once (1) per Refueling 619.4.022 1 receipt of Scram signal Cycle
- 2. Scram Stenal can be reset and Vent and Dra!4 At least once (1) per Refueling 619.4.022 D i Valves Open when the SDV Trip is bypassed Cycle A
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ATTACHMENT 1 (Cont.) Proc. 113 Rev. 16 ., .,
4.3 REACTIVITY COOLANT .
APPLICABLE TECHNICAL SPECIFICATION REQUIREMENT ACTUAL TEST FKnH N Y PGDCEDUREfS) SCHEDULE 4.3.A. Neutron Flux Monitor Test N/A - First RO Only ------ ------
4.3.8. NDE of Components Each Refueling Outage In-service D f Inspection Program 4.3.C. Reactor Coolant System Leak Test Each Refueling Outage 602.4.001 D 4.3.D. Safety Valve Bench Check Each Refueling Outage 702.1.002 D 702.1.005 SP 1302-12-155 SP 1302-12-161 4.3.E. Reactor Coolant Sample - 1/3 0 1/ Day 427.1 (A) Chem. Weekly
- 4.3.F. Core Spray Testable Check Valve Leakage Test Each Refueling Outage, or if the 610.4.011 C&D 150 < Rx Press < 600 plant is in cold shutdown for greater than 72 hrs and the test has not been performed in the proceeding 9 months.
e
ATTACHMENT 1 (Cont.) Proc. 116 Rev. 16 .
4.4 EMERGENCY COOLING REQUIRED ACTUAL APPLICA8LE TECHNICAL SPECIFICATION REQUIREMENT FREQUENCY f.R OJEMCY PROCEDURE SCHEDULE 4.4.A. Core Sorav System
- 1. Ptap Operability 1/Mo. Also after 1/ Month 610.4.002 A i major maintenance & Each Refueling Outage 610.4.002 D prior to startup following a refuel-ing outage.
- 2. Motor operated valve operability Once/ Month Once/Monti~. 610.4.003 A
- 3. Automatic actuation test Every 3 Months Once/ Month 610.3.005 A
- 4. Ptap compartment water-tight doors closed Once/ Week & after Once/ Month Reactor 81dg. R each entry Tour Sheet
- 5. Core Spray header Delta P instrumentation
- a. Check Once/ Day Once/ Day TS Log E M b. Calibrate Once/3 Months Once/3 Months 610.3.004 A Y c. Test Once/3 Months Once/3 Months 610.3.004 A
~
o 4.4.B. Autocatic Deoressurization
- 1. Valve Operability Every Refueling Each Refueling Outage 602.4.003 D Outage
- 2. Automatic Actuation Test Every Refueling Each Refueling Outage 602.3.005 0 Outage 4.4.C. Containment Coolina Svitem
- 1. Pump Operability 1/Mo. Also after 1/ Month 607.4.001 A major Maint. & prior to startup following Each Refueling Outage 607.4.001 0 a refueling outage.
- 2. Automatic Actuattru* Test Every 3 Months 1/ Month 607.3.002 A
- 3. Pump Compartment Water-ttght dors closed Once/ Week & after Once/ Day Reactor 81de. R each entry Tour Sheet
ATTACMMET I (Cont.) Proc. 116 Rev. 16 +
- 4.4 EMERGENCY COOLING (Continued)
REQUIRED ACTUAL APPLICABLE TECMMIrAL. SPECIFICATION REQUIREMENT FREQUENCY FREQUENCY PMICEDURE SCHEDULE 4.4.D. Emeraency Service Water System
- 1. Pump Operablitty 1/Mo. Also after 1/ Month 607.4.001 A major maint. & prior to startup following Each Refueling Outage 607.4.001 0 refueling outage.
- 2. Automatic actuation test Every 3 Months Once/ Month 607.3.002 A 4.4.E. Control Rod Drive Hydraulic System
- 1. Pump Operability 1/Mo. Also after Once/ Month 617.4.001 A major maint. & prior to startup following Each Refueling Outage 617.4.001 D a refueling outage.
4.4.F. Fire Protection System i U
, a 1. Pump ar.d Isolation Valve Operabtitty 1/Mo. Also after 1/Mo. (Valves), 610.4.007 A
[ major maint & prior 1/2 Weeks (Pumps) 645.4.001 A j to startup following a refueling outage. Each Refueling Outage 610.4.007 D 645.4.061 i
i 4
ATTACHMECT 1 (Cont.) Proc. 113 Rec. 10 4.5 CONTAINMENT SYSTEM REQUIRED ACTUAL APPLICABLE TECHNICAL SPECIFICATIDM REDUIREMENT FREOUENCY FREDUENCY PROCEDURE SCHEDULE 4.5.D. Integrated Primary Containment Leakage Rate Test Depends upon Now on 12 Mos t 8 666.5.007 0 whether any test Mos. Schedule g exceeds leak rate allowable-not to exceed 48mos. t amos.
Must be repeated in 12mos. If portion of test fatis.
4.5.E. Local Leak Rate Tests .
- l. Primary containment testable penetrations and Whenever opened and Each Refueling Outage 665.5.004 D tsolation valves. each Refueling Outage 665.5.006
- 2. Personnel air lock door seals. Each Refueling Outage Each Refueling Outage 665.5.005 0 tn 3. Contatraent components not included in 1 and 2 Each Refueling Outage Each Refueltne Outage 665.5.006 0 Y which required leak repairs following any
- integrated leakage rates in order to meet the
" allowable leakage rate untti Lt shall be subjected to local leak tests at a pressure of 35 pste at each refueling outage.
- 4. MSIV'a Each Refueling Outage Each Refueling Outage 665.5.003 D O
ATTACHMENT I (Cont.) Proc. 113 Rec. 13 4.5 CONTAINMENT SYSTEM (Continued)
ACTUAL APPLICABLE T[CHNICAL SPECIFICATION REQUIREMENT FREQUENCY PODCEDURE SCHEDULE 4.5.G. conttonanc Leak Rate Monitor
- 1. When the primary containment is inerted the Continuous Monitor ------ E ,
Checked I/ Shift containment shall be continuously monitored for gross leakage by review of the inerting system makeup requirements.
4.5.H. geoort of Test Results Each integrated leakage rate shall be the subject of 6#ien tests are 665.5.020 N/A a sumary technical report, performed 666.5.007 4.5.I. Functional Test of Valves
- 1. All containment isolation valves specified in Each Refueling Outage 619.3.004 O Table 3.5.2 shall be tested for automatic closure 619.3.003 e
by an isolation signal during each refuelina outane and are required to close in the time 642.4.003 C specified below:
Main Steam Line Isolation Valve 1 3 sec.Si 10 sec.
Isolation Condenser Isolation valves 1 60 sec.
Cleanup System Isolation valves 1 60 sec.
Cleanup Aux 111ary Pumps System Isolation Valves Valves 1 60 sec.
Shutdown System Isolation Valves 1 60 sec.
- 2. Each containment isolation valve shown in Table 3.5.2 shall be demonstrated operable prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator by cycling the valve. through one complete cycle and verify the isolation time.
MSIV's Post Maintenance 602.4.002 Post Maintenance Main Steam Condensate Drain Valves Post Maintenance 602.4.002 Post Maintenance Reactor Building Closed Cooling Valves Post Maintenance 642.4.002 Post Maintenance Instrtmeent Air Valve (V-6-395L Post Maintenance 652.3.001 Post Maintenance Emergency Cond. Valve Post Maintenance 609.4.001 Post Maintenance Reactor Cleanup Valves Post Maintenance 606.4.001 or Post Maintenance Post Maintenan a 606.4.001 or Post Maintenance anA a an? pact neatnt.nane.
% =
ATTACHMECT 1 (Cont.) Proc. 110 Rev. 10 4.5 CONTAINMENT SYSTEM (Continued)
ACTUAL APPLICASLE TECHNICAL SPECIFICATION REQUIREMENT FRE00EhCY PROCEDURE SCHEDULE Shutdown Cooling Valves Post Maintenance 613.4.002 Post Maintenance DWEDT Valves Post Maintenance 676.4.001 Post Maintenance Drywell Sump Valves Post Maintenance 676.4.001 Post Maintenance Drywell & Torus ATM - Control Valves V-23-13. V-23-14. V-23-15. V-23-16 Post Maintenance 678.4.001 Post Maintenance V-27-1. V-27-2 V-27-3 V-27-4. V-28-17 Post Maintenance 678.4.001 Post Maintenance V-28-18. V-23-21. V-23-22. V-28-47 Post Maintenance 604.4.016 Post Maintenance V-23-17. V-23-18. V-23-19. V-23-20 Post Maintenance 604.4.016 Post Maintenance Rx Rectre Loop Sample Valves Post Maintenance 678.4.002 Post Maintenance Torus to Rx Bldg Vac Relief Vahes Post Maintenance 604.4.003 Post Maintenance Traversing in Core Probe System Post Maintenance 678.4.001 Post Maintenance Folled ng maintenance repair or replacement work on the control or power circutt for the valves shown in Table 3.5.2 (see below) the affective components shall be tested to assure it will perform its intended function in the circuit.
tn Y MSIV's Post Maintenance 619.3.004 Post Maintenance g Post Maintenance Post Maintenance 621.3.003 619.3.010 Post Maintenance Post Maintenance Post Maintenance 619.3.005 Post Maintenance Post Maintenance 619.3.007 Post Maintenance Main Steam Condensate Dratn' Valves Post Maintenance 619.3.004 Post Maintenance Reactor Su11 ding Closed Cooling Valves Post Maintenance 642.4.003 Post Maintenance Instrument Air Valve (V-6-395) Post Maintenance 619.3.004 Post Maintenance Emergency Cond. Valve Post Maintenance 609.3.003 Post Maintenance Post Maintenance 619.3.004 Post Maintenance Post Maintenance 609.3.002 Pof.t Maintenance Reactor Cleanup Valves Post Maintenance 619.3.003 Post Maintenance Post Maintenance 619.3.004 Post Maintenance Shutdown Cooling Valves Post Maintenance 619.3.003 Post Maintenance Post Maintenance 619.3.004 Post Maintenance DWEDT Valves Post Maintenance 619.3.003 Post Maintenance Post Maintenance 619.3.004 Post Maintenance Drywell Sump Valves Post Maintenance 619.3.003 Post Maintenance Drywell s Torus ATM - Control Valves Post Maintenance 619.3.003 Post Maintenance Post Maintenance 619.3.004 Post Maintenance Rx Recirc Loop Sample Valves Post Maintenance 619.3.004 Post Maintenance
( Torus to Rx Bide. Vac Relief Valves Post Maintenance 619.3.003 Post Maintenance Post Maintenance 619.3.004 Post Maintenance Traverstng in Core Probe System Post Maintenance 619.3.003 Post Maintenance Post Maintenance 619.3.004 Post Maintenance
ATTACHMECT I (Cont.) Proc. 113 Rev. 13 4.5 CONTAINMENT SYSTEM (Continued) , ,
ACTUAL APPLICABLE TECHNICAL SPECIFICATION REDUIREMENT TEST FRE0uENCY P E EDdRE SCHEDdLE 4.5.I. 3. During periods of sustained power operation each main steamitne isolation valve shall be excercised in accordance with the following j schedule.
- a. Daily tests - Exercise valve (1 at a time) Daily 602.4.006 E to approx. 95% open position with reactor at operation power level.
- b. Quarter 1v tests - Trip valve (I at a time) 1/ Quarter 602.4.002 A&C and check full closure time, with reactor power not greater than 50% of rated power.
- 4. Reactor Butidina to Sunaression Chamber Vacuum Breakers
- a. Operability Check - 1/3 mos. 1/3 Months 604.3.001 A (Inst.Calth.)
604.4.002 A g (operability) 604.4.015 A a
(Operability)
G
- b. Determine Opening Force Each Refueling Outage 604.4.003 D (Test) 604.3.001 (Calth.)
- 5. Pressure Gnaression Cb " r - Drvwell Vacuum Breakers
- a. Periodic Goerability Tests 1/Honth 604.4.006 A 604.4.016 0 j b. Refuelina Outaae Tests
- 1. All suppression chamber - drywell vacuum Each Refueling Outage 604.4.016 0 breakers shall be tested to determine the (and 1/3 mos.)
force required to open each valve from fully closed to fully open.
i 2. The suppression chamber - drywell vacuum Each Refueling Outage 604.1.005 0 breaker position indication and alarm (Calib.)
systems shall be calibrated and i
functionally tested. 604.4.006 i 1. At least four of t'he suppression chamber - Each Refueling Outage 704.1.004 D drywell vacuun breakers shall be inspected i
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- e 4.5 C3NTAINMENT SYSTEM (Continued)
ATTACHMENT 1 (Cont.) Proc. 116 Rev. 15 ACTUAL APPLICA8LE TECHNICAL SPECIFICATION REOUIREMENT TEST FREQUENC1r PMICEDURE SCHEDULE 4.5.I. 4. Drywell to suppression chamber leak rate Each Refueline Outage 665.5.061 D test 4.5.J. neactor Butidina 1
- 1. Secondary Containment Capablitty Each Refueling Dutage 665.5.002 0
- 2. Secondary Containment Capability - e,ce per Each Refueling Dutage 665.5.002 0 Operating Cycle
- 3. Secondary Containment Capability - prior to Each Refueling Dutage 665.5.002 D refueling
- 4. Test Report N/A N/A N/A 4.5.K. Standhv Cas Treatment System 1.a The capability of the SGTS shall be vertfled, at least once per 18 months, after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of operation and following significant
[3 painting. fire or chemical release in the a
Es Reactor Building during operation of SGTS.
- 1. Charcoal Filter Efficiency HEFA Ftiter 1/18 Months 651.3.002 8 Efficiency (HEPA) 651.3.003 (Charcoal)
- 2. Laboratory Cerbcn Sample Analysts 1/18 Mcnths 651.1.006 8 1.b.1. Delta P Demonstration - 1/18 months 1/ Month 651.4.001 A 1.b.2. Heater Capability - 1/18 months 1/18 Months 651.2.004 B 1/ Month 651.4.001 A 1.b.3. Flow Test - 1/18 months Refueling Outage 665.5.002 1.c. 10 Hour Test - 1/30 days 1/ Month 651.4.001 A 1.d. Filter Bank Test - When Filters are partially When Filters are 651.3.002 N/A or completely replaced Replaced (HEPA) 651.3.003
. (Charcoal) 1.e. Automatic Actuation - 1/18 mos. 1/ Month 651.4.001 A
-- . - . - .~ . _ , _-. -- - - - - -
4.5 CDETAINMENT SYSTEM (Continued) 4 ATTACMMENT 1 (Cont.) Proc. 116 Rev. 10 .
ACTUAL' APPLICA8LE TECHNICAL SPECIFICATIDN REDUIREMENT TEST FREQUENCY PMDCEDURE SCHEDULE 4.5.L. DELETED 4.5.M. Inerting Surve111ance - Check 0: Weekly Once/ Week (Calib.) 604.3.009 A f t
4.5.N. Drywell Coating Surveillance - 1st, 2nd, 4th & 8th N/A R.O. i 4.5.0. Instrument Line Flow Check Valve Isolation Capability Each Refueling Outage 604.3.008 0 Verify Open Position During Various Instrument ------- Each -----
Surveillances Respective l Procedure i
4.5.P. Caaressian cb- ' r Surveillance E 1. Level Temperature and Pressure - Check 1/ Day 1/ Shift TS Los Sheet E
$ 2. Suppression Chamber Interior Visual Inspection - Each Refueling Dutage 704.1.013 D at Each Major Refueling Outage
- 3. Suppression Pool Temperature (during heat N/A 2000-RAP-3024.0; N/A
, addition) 2000-0PS-3024.13 i 4. Suppression Chamber Exterior Visual Inspection As required by Spec. 604.4.013 N/A
! after reitef valve operation and the pool 160*F 2000-OPS-3024.13 and the reactor coolant is 180 PSIG.
I 4.5.Q. Shack Sunnressors (Snubbersl
- 1. Hydraulic Snubber Inspect 5on Depends on Failure 675.1.001 D Rate. Follow Tech
', Spec Requirements
- 2. Initial Inspection N/A ---- ------ l
- 3. 31 Day Inspection 675.1.001 ------
}'
- 4. Functional Test - Each Refueling Cycle Each Refueling Outage 775.1.005 D i
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4.0 RADI0 ACTIVE EFFLUENTS .
ATTACHMENT 1 (Cont.) Proc. 113 Rev. 16 ,
ACTUAL APPLICA8LE TECHNICAL SPECIFICATION REDUIREMENT TEST FREQUENCY PIWCEDURE SCHEDULE 4.6.A. The stack gas radiation monitoring channels shall Checked 1/S Tech Spec Los E be checked dally, ttsted monthly, and calibrated Tested I/ Month 621.4.086 A every three months. Calibrated 1/3 Mos. 621.3.084 A The radwaste 11guld effluent radiation monitoring Checked 1/S 621.4.013 E channel shall be checked daily, tested monthly and Tested 1/ Month 621.3.012 A calibrated every 3 months. Calibrated 1/3 Mos. 621.3.014 A i
4.6.B. 1. Stack Release
- a. Stack Gaseous Release Rate & Meteorological Recorded Hourly Reactor -----
Condttion - Nourly Aux 111ary Log Environmental Data Log
- b. Isotopic Analysis Following Refueling Re W t Satisfied by 829.4 4.6.B.1(d)
- c. Offgas Sample With Activity Determined - 3 Times / Week 829.1 Chem. Weekly Every % Hours CI d. Offgas Isotopic Arnlysis 3 Times / Week 829.1 Chem. Weekly
$- e. Gaseous Release of Tritium - 1/3 Months Once/ Month 829.5.1 Chem. Monthly
- f. Records of Iodine an.' Particulate Twice/ Week 829.3 Chem. Weekly
- g. Cartridge Analysts Twice/ Week 829.3 Chem. Weekly
- h. When Gross Release Rate Increases by 50%
Analyze Cartridge Twice/ Week 829.3 Chem. Weekly
- 1. Iodine and Particulate Isotopic Analysis - Qtr Twice/ Week 829.3 Chem. Weekly
- 2. Liouid Release .
c a. Record of Radioactive Concentration and Voltme Batch Basis 830.4 -----
for Release
- b. Proportional Composit for Each Batch Released Once/ Week 830.3 Chem. Weekly Weekly
- c. Proportional Composit for Each Batch Released Once/ Month 830.3 Chem. Monthly Monthly
- d. Quarterly Proportional Composite for SR-90 Once/ Month 830.3 Chem. Monthly
- e. Effluent Analysis .
Each Liquid Release 830.4 -----
- f. Identified Radionuclide Analysts Each Liquid Release 830.4 -----
i
ATTACHMENT 1 (Cont.) Proc. 116 Rev. 10
- 4.6 RADIOACTIVE EFFLUENTS (Continued)
ACTUAL APPLICA8LE TECHNICAL SPECIFICATION REOUIREMENT TEST FREQUENCY PAGCEDURE SCHEDULE I
- 3. Environmental Proaram The environmental program described in Section l.
B.ll.6 of Amendment 65 to the application for a reactor operating license shall be conducted.
4.6.C. Reactor Coolant Radioactive Iodine Analysts - Once/ Day 827.I Chem. Weekly Every 72 Hours 4.6.D. Waste Sample Tanks. Floor Drain Sample Tanks and 3 Times / Week 830.4 Cheel. Weekly the Waste Surge Shall be Sampled and Analyzed Every 72 Hours 4.6.E. Radwaste Equipment Operabiltty vertfted 1/ Quarter Once/Qtr 830.1 Chem. Yearly g
Y Chem. Monthly 829.3 5 4.6.F. 1. Gaseous Release Calculations per 3.6.F. Once/ Month
- 2. Particulate Release Calculations per 3.6.F. Once/ Month 829.3 Chem. Monthly i
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ATTACHMEUT I (Cont.) Proc. 113 Rev. 10- ,
4.7 AUXILIARY ELECTRICAL POWER REQUIRED ACTUAL APPLICABLE TECHNICAL SPECIFICATION REDUIREMENT FREOUENCY TEST FREDUENCY PEDCEDURE SCHEDULE 4.7.A. Diesel Generator
- 1. Diesel Generator 20% Load Test Every 2 Weeks 1/2 Week 636.4.003 A f i 2. Diesel Generator Actuation and Functiom) Test Each Refueling Outage Each Refueling Outagt 636.2.001 0
- 3. Diesel Generator Inspection 1/18 Mcnths 1/18 Months 736.1.006 D
- 4. Diesel Generator' Fuel Supply Check Checked Following After Each Test Above Same as above Same as above Above Tests
- 5. Diesel Generator Batteries Same as Station See 4.7.B *Ve 4.7.B
. See 4.7.B Batteries g 4.7.B. Station Batteries to Weekly Station A 4
o
- 1. Pilot Cell Test 1/ Week Batteries /
634.2.002 634.2.004 D.G Batteries /
636.2.005
- 2. Cell Voltage Test / Cell Electrolyte Test Quarterly 1/ Month 634.2.003/ A 636.2.006 634.2.005
- . Battery Capacity Discharge Test 1/18 Mos. When Shut- 1/18 Months 634.2.001/ B down 636.2.004 634.2.006 i
l l
ATTACHMENT 1 (Cont.) Proc. 116 Rev. 15 ,
8, . ? I'AtATli1 L3NDENSER REQUIRED ACTUAL APPLICABLE TECHNICAL SPECIFICATION REQUIREMENT FREOUENCY TEST FREQUENCY PROCEDURE SCHEDULE 4.8.A. Surveillance of each isolation condenser loop shall be as follows:
- 1. Operahtitty of motor operated isolation valves once/ Month 1/ Month 609.4.001 A and condensate makeup valves.
- 2. Automatic actuation and functional test Each refueling outage Each refueling outage 609.3.003 0 Following major repair
- 3. Shell side water volume check Once/ day 1/ Shift, Tech Spec E Los Sheet
- 4. Isolation valve (steam side)
- a. Visual inspection Each refueling outage Each refueling outage ISI Program. D 602.4.001 and 609.1.005 C b. External leakage check Each primary system Each leak test 602.4.001 D 4 leak test
- c. Area temperatures check Once/ Shift 1/ Shift Tech Spec E Los Sheet I
- 6 4.9 REFUEmING .
ATTArt:ME:5T 1 (Cont.) Proc. 115 Rev. 15 ACTUAL APPLirCA8LE TECHNICAL SPECIFIC ATION REQUIREMENT TEST FREDUENCY PlWCEDURE SCHECULE 4.9.A. 1. Refueling Interlock lest (Prtor to fuel handling) Prior to fuel handling 656.4.001 D
- 2. Refueling interlock Weekly Test Once/ Wee. 656.4.001 (205.0)
Sec. 8.2.5 l'
4.9.8. 1. SRM calibration prior to core alterations Calibrated pric* to 620.3.006 D core alterations
- 2. SAM daily check Daily Check S/D Los - F Hourly (205.0)
Sec. 2.7.1.2
- 3. SSM monthly test Weekly Test 620.4.004 o (205.0)
Sec. 3.2.4
! 4. SEM Quarterly Calibrated Weekly 620.4.004 U. 4.9.C. Four hours prior to control rod removal per 3.9.E 4
- U 1. Rx mode switch /one rod out refueling interlock Frior to control rod (205.4)S/D Log R removal
- 2. Two (2) SAM channels operable Prior to control rod (205.4)S/D Log R 1 removal 4.9.D. Four hours prior to control rod removal per 3.9 F.
j and daily thereafter
- 1. Rx mode switch /one rod out refueling interlock
! a. Vertfled prior to control rod removal Prior to control rod 205.4 S/D Log R j removal
) b. Checked daily thereafter Daily 205.4 S/D Log R 2 (Refueling l j Interlock) ,
t
- 3. All control rods not removed are tully inserted. 205.4 D f 4. Four fuel assemblies removed Daily 205.7 R i 205.22
- . 205.25 Sec. 5.2 i __
1 i
b i.
1-i a
4 l
ATTACHMECT 1 (Cont.) Proc. 113 Rev. 13 l
4.9 REFUELING (Continued)
I I
ACTUAL APPLICABLE TECHNICAL SPECIFICATION REQUIREMENT TEST FREGRENCY PMICEDURE SCHEDULE i a l
4.9.E. 25% Delta K Shutdown Martin Pri'or to Control Rod Satisfied by performance of 1001.26 Removal per 3.9.F. .e 1001.27 done at end of previous
. outage. Specification 4.2.A. g 4.9.F. Refueling Interlock Restored Following Replacement
~
205.7 Sec.5.3 is of % ntrol Rod or Rod Drive - Prior to Inserting Fuel in the Control Cell.
i NOTE: No schedule exists to ensure daily requirements are satisfied.
, tJe iN
- LJ l
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i 4
0 ll 4
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ATTACHMECT 1 (Cont.) Proc. 116 Rev. 13 ,
4.10 ECCS KLATED CORE LIMITS ACTUAL APPLICA8LE TECHNICAL SPECIFICATION REQUIREMENT TEST FRE0uENCY PROCEDURE SCHEDULE 4.10.A. Average Planar LNGR - Checked Daily Daily 1001.33 A 4.10.B. Local LHGR - Checked Detly Daily 1001.33 A 4.10.C. Minimum Critical Power Ratto (MCPR) - Checked Daily Daily 1001.33 A b
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ATTACHMC:T I (Cont.) Proc. 116 Rev. 15 d-e' 4.11 SEALED SOURCE CONTAMINATION ACTUAL APPLICABLE TECHNICAL SPECIFICATION REOt11REMENT TEST FREQUENCY P MCEDURE SCHEDULE 4.11.A. Radioactive Source Contamination Test See below 4.11.B. Source Test Frequency
- 1. Sealed Source Contamination Survey - Every 1/6 Months HP Form 901 Rad. Protection 6 Months.
- 2. Stored Sealed Sources - Prior to Use or Transfer N/A Unless Tested in the Last 6 Months.
- 3. Startup Sources - Prior to and Following Repairs N/A or Modification and with 31 Days Before Beine Subjected to Core Flux.
E b
i I .. o l ATTACHMENT 1 (Cont.) Proc. 116 Rev. 13 . g 1 .
l 4.12 FIRE PROTECTION l
REQUIRED ACTUAL APPLICABLE r TECHNICAL SPECIFICATION REQUIREMENT EREQUDICI TEST FREQUENCY PROCEDURE SCHEDULE 4.12.A. Fire Detection Instrimantating
- 1. Fire detection instrumentation channel functional 1/6 mos. S 645.6.005 B test.
- 2. Operability of detection alarms of the fire 1/6 mos. S 645.6.005 8 detection instruments.
B. Fire Sungression Water System f 1. Fire Suppression Water System Operable
- a. Staggered pump operabtitty test 1/mo. SH 645.4.001 A
- b. Valve line up verification 1/mo. M 645.6.004 A
!@ c. System flush 1/yr. S 645.6.007 8 I
- o. Cycling valves 1/yr. Y 645.6.009 8
- e. Pump functional test 1/18 mos. X 645.6.012 B
- f. Flow test per NFPA 1/3 yrs. 2 645.6,023 8
- 2. Itre Diesel Engine Operable
- a. Fuel storage tank level check 1/mo. W 645.4.001 A 4
- b. Diesel engine operability 1/mo. SM 645.4.001 A A
- c. Diesel fuel analysis 1/3 mos. Q 803.52 8
- 3. Fire Diesel Battery Vertftcation
- a. Weekly check 1/wk. W 645.2.002 A
- b. 3 month check 1/3 mos. M 645.2.002 A c.18 month visual inspectior. 1/18 mos. W/M 645.2.002 A
q .
ATTACHMECT 1 (Cont.) Proc. 113 Rev. 16 ,
j l . /
4.12 FIRE PROTECTION (Continued)
REQUIRED ACTUAL APPLICABLE TECHNICAL SPECIFICATION REOUIREMENT fjiQUENCY TEST FREQUEMCY PlWCEDURE SCHEDULE C. SPRAY AND/OR SPRINKLER SYSTEMS
- 1. a. System functional test 1/18 mos. X 645.6.010 B
- b. Water header inspection 1/18 mos. X 645.6.011 B
- c. Spray nozzle inspection 1/18 mos. X 645.6,011 B D. Hose Stations
- 1. a. Hose station visual inspection 1/mo. M 645.6,003 A
- b. Hose inspection and reracking 1/18 mos. X 645.6,008 B
- c. Hose flow blockage and hydrotest 1/3 yrs. Z 645.6.006 B s
E. Penetration Fire Barrier U 1. a. Fire barrier visual inspection 1/18 mos. X 645.6.017 8
- b. Fire barrier visual inspection following Post-maintenance Post-meintenance 645.6.017 B repairs or maintenance F. Low Pressure Carbon Dioxide (CO2) System
- a. CO2 storage tank level check 1/wk W 645.6.015 A
- b. Valve position vertftcation 1/mo. W 645.6.015 A
- c. 1. Verify automatic actuation of the system 1/18 mos. X 645.6.016 B valves and ventilation damper
- 2. Verify nozzle flow during " Puff Test" 1/18 mos. X 645.6.016 8 G. Halon Systaans
- 1. a. Halon storage tank weight or level and 1/6 mos. S 645.6.014 8 pressure verification
- b. 1. Verify the automatic actuation of the system 1/18 mos. X 645.6.013 8
- 2. Flow blockage test 1/18 mos. X 645.6.013 8 l
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ra a ATTACHMENT I (Cont.) Proc. 116 Rev. 10 , 7 o
f 4.12 FIRE PROTECTION (Continued)
REQUIRED ACTUAL APPLICABLE TECHNICAL SPECIFICATION REQUIREMENT fBEQUENCY TEST FREDUENCY PROCEDURE SCHEDULE H. Yard Fire Hydrants and Hydrant Hose Houses l
- 1. a. Visual inspection for required equipment 1/31 days M 645.6.003 A
- b. Visual inspection of fire hydrant and the 1/6 mos. M 645.6,003 A hydrant barrel
- c. 1. Yard hose test 1/12 mos. Y 645.6.006 B
- 2. Coupline gasket inspection 1/12 mos. Y 645.6.006 8
- 3. Hydrant flow check I/12 mos. S 645.6,007 8 b
9
- ATTACHME::T I (Cont.) Proc. 115 Rev. 15 f, i f 4.13 ACCIDENT MONITORING INSTRUMENTATION ACTUAL APPLICA8tE TECHNICAL SPECIFICATION REOUIPEMENT TEST FREQUENCY PADCEDURE SCHEDULE 4.13.A. Primary Detectors (Acoustic)
- 1. Monthly Channel Check 1/Mo. 602.3.008 A
- 2. Channel Calibration 1/18 mo. 1/18 Mos. 602.3.009 8 and 0 4.13.8. Backup Detectors (Thermocouples)
- 1. Monthly Channel Check 1/Mo. 602.4.011 A
- 2. Channel Calibration 1/18 mo. 1/18 Mos. 602.3.012 B and D 1
4.13.C. Comenon Header Temperature Element
- 1. Monthly Channel Check At least 1/15 Days 602.4.011 A untti channel ca11b.
is complete and then 1/31 days.
, 2. Channel Calibration 1/18 mo. 1/18 Mos. 602.3.012 8 and D i
a t4 I
nB 1
1 1
1
)
l 1
L j
ATTACHMENT 1 (Cont.) Proc. 115 Rev. 15 -
6.15 INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT ACTUAL APPLICABLE TECHNICAL SPECIFICATION REQUIREMENT TEST FREQUENCY PROCEDURE SCHEDut.E 6.15 Implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious accident t to as low as practical 'evels.
- 1) Preventive maintenance and periodic visual inspection.
l 2) System leak test, to the extent permitted by system design and radiological conditions, for each system at a frequen:;y not to exceed refueling cycle intervals. The systems subject to testing are:
- 1) Core Spray
- 2) Containment Spray g 3) Reactor Water Cleanup b
.o
- 4) Isolation Condenser
- 5) Shutdown Cooling e
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