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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20203H7501997-08-19019 August 1997 Rev 10 to Radiological Environ Monitoring Program Manual ML20203H7351997-02-10010 February 1997 Rev 9 to CAP-0002, Off-Site Dose Calculation Manual ML20203H7231997-01-21021 January 1997 Rev 9 to Radiological Environ Monitoring Program Manual ML20059C1861993-12-22022 December 1993 Proposed Tech Specs Amend 186,rev 1 Re Nuclear Organizational Changes ML20058L4371993-12-0909 December 1993 Proposed Tech Specs Amend 187 Including Changes Making PDTS Consistent W/New 10CFR20 Regulations ML20127N3671993-01-19019 January 1993 Proposed Tech Specs Section D6.0,administrative Controls for Proposed Amend 186 ML20059E0191990-08-0303 August 1990 Rev 0 to CAP-0002, Odcm ML20059E0141990-01-31031 January 1990 Rev 0,App a to CAP-0002, Odcm ML20059E0241989-11-22022 November 1989 Rev 3 to Environ Monitoring & Emergency Preparedness ML20246A4081989-08-16016 August 1989 Rev 5 to Inservice Testing Program Plan ML20245L7281989-07-18018 July 1989 Rev 5 to Administrative Procedure RSAP-0101, Nuclear Organization Responsibilities & Authorities ML20246F1241989-07-0505 July 1989 Proposed Tech Specs,Deleting App B in Entirety ML20246A5221989-06-30030 June 1989 Closure Plan ML20245H5781989-06-22022 June 1989 Proposed Tech Specs for Amend 109 to License DPR-54 ML20246E8551989-04-30030 April 1989 Analysis of Capsule RS1-F Smud Reactor Vessel Matl Surveillance Program ML20245L0461989-04-27027 April 1989 Proposed Tech Specs for Proposed Suppl 1 to Amend 134 Re Application for Amend to License DPR-54,clarifying Unacceptability of Analysis Allowing Imperfections Greater than 40% of Nominal Tube or Sleeve Wall Thickness ML20235Y6071989-03-0606 March 1989 Proposed Tech Spec Page 4-17,including one-time Extension for Certain Surveillances Required to Be Performed by 890329 ML20245G1941989-02-28028 February 1989 Procurement Engineering Assessment Plan Final Rept ML20245H8911989-02-28028 February 1989 Revised Proposed Tech Specs,Including Pages 3-30a,3-30b, 3-40a,3-45,3-46,4-18a & 4-75 Re Addition of Operating Requirements Designed to Provide Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations ML20195F7701988-11-18018 November 1988 Proposed Tech Spec Section 3.4, Steam & Power Conversion Sys ML20206F2881988-11-15015 November 1988 Proposed Tech Specs 4.6.4.f (Page 4-34i) Re Surveillance of Equipment Required to Verify Vital 120 Volt Ac Bus Operability ML20205R8681988-11-0404 November 1988 Proposed Tech Specs Re Local Leakage Rate Tests & Reactor Bldg Containment Integrity ML20205M8971988-10-28028 October 1988 Proposed Tech Specs Re Nuclear Svc Battery Operability & Surveillance Requirements ML20205L2661988-10-25025 October 1988 Proposed Tech Spec Table 3.14-3, Carbon Dioxide Suppression Zones ML20155G2201988-10-0707 October 1988 Proposed Tech Specs Clarifying Operational Mode Applicability of Tech Spec 3.4 & Definition of Auxiliary Feedwater Sys Train ML20155B8481988-09-30030 September 1988 Proposed Tech Specs Re Reactor Protection Sys Trip Setting Limits,Rcs High Point Vents,Leakage & Leak Detection,Reactor Coolant Inventory & Auxiliary Electric Sys ML20155B4591988-09-30030 September 1988 Proposed Tech Spec Sections 1,3,4,5 & 6,reflecting Numerous Editorial Corrections & Administrative Changes ML20206A8151988-09-28028 September 1988 Rev 0 to, Effluents & Water Mgt Project Action Plan ML20154J5611988-09-19019 September 1988 Proposed Tech Specs,Changing Local Leak Rate Test Requirements for Containment Penetrations ML20154D7591988-09-0808 September 1988 Proposed Tech Specs Re Administrative Controls,Onsite & Offsite Organizations & Facility Staff ML20153E6481988-08-31031 August 1988 Proposed Tech Specs on Limiting Condition for Operation Re Containment Isolation Valves ML20151K1041988-07-28028 July 1988 Rev 0 to Special Test Procedure STP.668, EFIC High/Medium Decay Heat Test ML20207C0831988-07-27027 July 1988 Revised Proposed Tech Specs,Consisting of Rev 1 to Proposed Amend 102,deleting App B ML20151H6131988-07-15015 July 1988 Rev 0 to Matl Control Dept Action Plan for Rancho Seco Nuclear Generating Station ML20196A2281988-06-21021 June 1988 Proposed Tech Specs Providing Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations During Power Operation & Modifying Existing Purge Sys Operation Requirement ML20155K0971988-06-14014 June 1988 Proposed Tech Specs Making Minor Corrections to Table 3.5.5-1, Accident Monitoring Instrumentation,Items 5 & 14 & Table 4.1-1 Items 65 & 92 & Adding Second Note to Table 4.1-1,Item 80 ML20195J4921988-06-10010 June 1988 Proposed Tech Spec Pages 4-69 Through 4-85a,modifying Radiological Effluent Tech Specs to Reduce Count Time Required for prebatch-release Sample Analysis ML20151R0641988-04-15015 April 1988 Rev 0 to STP.1154, Remote Shutdown Panel Test ML20151X3211988-04-0606 April 1988 Rev 1 to Procedure Development Project Action Plan for Temporary & Interim Procedure Change Incorporation as Procedure Rev ML20151V5871988-04-0202 April 1988 Rev 1 to Sys Engineering Action Plan SYSTEM-012, CRD Breaker Action Plan ML20151X2871988-03-31031 March 1988 Rev 0 to Sys Engineering Action Plan SYSTEM-009, Letdown Cooler Thermal & Hydraulic Shock Prevention ML20150D1861988-03-17017 March 1988 Proposed Tech Specs,Correcting Typos & Making Further Editorial Changes to Proposed Amend 139,dtd 860129 ML20196G5131988-03-0101 March 1988 Proposed Tech Specs,Revising Tech Spec 4.1-1,Item 44.c & Tech Spec 4.10.1.E.2 Re Total Quantity of Gaseous Chlorine in Restricted Area ML20147F0771988-02-25025 February 1988 Revised Proposed Tech Spec Table 4.1-1 & Tech Spec 4.10.1.E.2,requiring Performance of Surveillances Only When Gaseous Chlorine Onsite ML20147B1761988-02-15015 February 1988 Rev 0 to RECM-6878, Radiological Effluent Control Manual ML20148D9931988-02-12012 February 1988 Post-Trip Transient Investigation,Assessment & Reporting ML20149K8621988-02-12012 February 1988 Proposed Tech Spec 6.5.1.6.d,identifying Items Not Requiring Plant Review Committee Review ML20196D9091988-02-11011 February 1988 Proposed Tech Specs,Adding Term Dewatering to Process Control Program ML20149G1781988-02-0808 February 1988 Proposed Page 3-19 to Tech Spec 3.3, Emergency Core Cooling,Reactor Bldg Emergency Cooling & Reactor Bldg Spray Sys ML20196B8071988-02-0101 February 1988 Proposed Tech Spec Figure 6.2-2, Nuclear Organization Chart 1997-08-19
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20203H7501997-08-19019 August 1997 Rev 10 to Radiological Environ Monitoring Program Manual ML20203H7351997-02-10010 February 1997 Rev 9 to CAP-0002, Off-Site Dose Calculation Manual ML20203H7231997-01-21021 January 1997 Rev 9 to Radiological Environ Monitoring Program Manual ML20059E0191990-08-0303 August 1990 Rev 0 to CAP-0002, Odcm ML20059E0141990-01-31031 January 1990 Rev 0,App a to CAP-0002, Odcm ML20059E0241989-11-22022 November 1989 Rev 3 to Environ Monitoring & Emergency Preparedness ML20246A4081989-08-16016 August 1989 Rev 5 to Inservice Testing Program Plan ML20245L7281989-07-18018 July 1989 Rev 5 to Administrative Procedure RSAP-0101, Nuclear Organization Responsibilities & Authorities ML20246A5221989-06-30030 June 1989 Closure Plan ML20245G1941989-02-28028 February 1989 Procurement Engineering Assessment Plan Final Rept ML20206A8151988-09-28028 September 1988 Rev 0 to, Effluents & Water Mgt Project Action Plan ML20151K1041988-07-28028 July 1988 Rev 0 to Special Test Procedure STP.668, EFIC High/Medium Decay Heat Test ML20151H6131988-07-15015 July 1988 Rev 0 to Matl Control Dept Action Plan for Rancho Seco Nuclear Generating Station ML20151R0641988-04-15015 April 1988 Rev 0 to STP.1154, Remote Shutdown Panel Test ML20151X3211988-04-0606 April 1988 Rev 1 to Procedure Development Project Action Plan for Temporary & Interim Procedure Change Incorporation as Procedure Rev ML20151V5871988-04-0202 April 1988 Rev 1 to Sys Engineering Action Plan SYSTEM-012, CRD Breaker Action Plan ML20151X2871988-03-31031 March 1988 Rev 0 to Sys Engineering Action Plan SYSTEM-009, Letdown Cooler Thermal & Hydraulic Shock Prevention ML20147B1761988-02-15015 February 1988 Rev 0 to RECM-6878, Radiological Effluent Control Manual ML20148D9931988-02-12012 February 1988 Post-Trip Transient Investigation,Assessment & Reporting ML20196B6901988-01-31031 January 1988 Rev 0 to Radiological Effluents Action Plan ML20149E2771988-01-29029 January 1988 Rev 4 to Inservice Testing Program Plan for Pumps & Valves ML20196C8521988-01-27027 January 1988 Rev 2 to Procurement Engineering Assessment Plan ML20148T0071988-01-20020 January 1988 Rev 1 to STP.961, Loss of Offsite Power ML20147H9261988-01-13013 January 1988 Rev 2 to Monthly Surveillance Test of Control Room/ Technical Support Ctr Essential Ventilation Sys Loop A. W/One Oversize Drawing ML20147H8771988-01-13013 January 1988 Rev 3 to Refueling Interval,Special Frequency Control Room/ Technical Support Ctr Essential HVAC Sys Actuation by Rad Monitors & Chlorine Detectors Train a ML20234F4601987-12-21021 December 1987 Rev 5 to AP.310, Offsite Dose Calculation Manual ML20236U1391987-11-20020 November 1987 Emergency Operating Procedure Technical Basis EOP POM-248 ML20236P5221987-11-13013 November 1987 Rev 0 to Special Test Procedure STP.961, Loss of Offsite Power Test ML20236Q0601987-11-10010 November 1987 Rev 1 to Radiological Environ Monitoring Program Manual ML20236X3591987-10-31031 October 1987 Rev 3 to Wire & Cable Program Rept ML20236L1481987-10-30030 October 1987 Rev 4 to Procedure AP.310, Offsite Dose Calculation Manual ML20236P1941987-10-14014 October 1987 Rev 1 to STP.660, Integrated Control Sys Tuning at Power ML20236D3191987-10-0707 October 1987 Rev 0 to Radiological Environ Monitoring Program Manual ML20236B7491987-09-23023 September 1987 Rev 1 to D-0050, Engineering Action Plan ML20235Q7561987-09-0303 September 1987 Twelve Sys Expanded Assessment of Expanded Augmented Sys Review & Test Program Rept ML20234C2331987-09-0101 September 1987 Motor-Operated Valves Program ML20235Z5811987-08-31031 August 1987 Rev 2 to Wire & Cable Program Rept ML20235N8631987-08-26026 August 1987 Rev 0 to Surveillance Procedure SP.486, Monthly Control Room/Technical Support Ctr Ventilation Gas Monitor Test ML20238E2451987-08-24024 August 1987 Rev 1 to Maint Administrative Procedure MAP-0009, Preventive Maint Program ML20235U0581987-08-18018 August 1987 Procedure AP.2.07, Verification of Emergency Operating Procedures ML20235U0461987-08-18018 August 1987 Procedure AP.2.06, Validation of Emergency Operating Procedures ML20237L6371987-08-12012 August 1987 Sys Review & Test Program Mgt Overview Manual ML20238D5981987-08-0606 August 1987 Rev 0 to ADM-0037, Maint Administrative Procedures Manual ML20235N5461987-08-0606 August 1987 Rev 1 to Surveillance Procedure SP.485A, Refueling Interval,Special Frequency Control Room/Technical Support Ctr Essential HVAC Sys Actuation by Rad Monitors & by Chlorine Detectors Train a ML20236J7071987-07-15015 July 1987 Expanded Augmented Sys Review & Test Program (Easrtp) Evaluation Plan ML20236J6921987-07-15015 July 1987 Expanded Augmented Sys Review & Test Program Methodology Guidelines ML20216H8221987-06-25025 June 1987 Rev 3 to Inservice Testing Program Plan,Rancho Seco Nuclear Generating Station ML20238E2501987-06-23023 June 1987 Rev 3 to Inservice Testing Program Plan for Pumps & Valves ML20214K3051987-04-24024 April 1987 Nuclear Records Mgt ML20214K2981987-04-24024 April 1987 QA Records 1997-08-19
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PROCEDURE DEVEI4PMENT PROJECT ACTION PIAN FOR TEMPORARY AND INTERIM PROCEDURE CHANGE INCORPORATION AS PROCEDURE REVISION REVISION 1 ,
APRIL 6, 1988 l
4 w h 'lM-6 rant Yelliott wy Manager, Pr6c'edure Development
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,; Director, Management Systems I i
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INDEX i t
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.l.. Introduction 1 [
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- 2. Action Plan 1 !
l j 3. Interia Migration Plan 2 l b
- 4. Long Tara Action Plan 3 !
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EXECUTIVE
SUMMARY
The completion of the recent outage and initial power ascension !
i has resulted in a large number of temporary and interim changes to Station Procedures per RSAP-0507 Change Notices to Procedures.
The following is a summary of a three-phase approach to incorporate these changes into procedure revisions.
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.. . .e 1.0 Introduction >
This action plan provides the method used to ensure applicable procedure changes are incorporated as procedure revisions. Temporary and interim changes are approved methods for temporarily changing procedures for a 90 day .
duration prior to incorporation as a revision.
2.0 Action Plan 2.1 Daily Fast Action Response A. Operations Department Procedures o Staff dedicated to incorporating changes 4 o Total precedures with outstanding changes 78 B. Surveillance Procedures o 21 surveillance scheduled to be run between 04/07/88 and 05/01/88.
o 8 of these 21 surveillance have changes i o 3 of these 8 have been incorporated as revisions. i o 5 of these 8 are being incorporated prior to the scheduled performance date or prior to l their expiratien date. )
o 30 other surveillances due to be run beyond 1 05/01/88 will have changes incorporated 5 l days prior to the run date or 30 days prior te their expiration of the temporary or interim !
change. l C. Operating Procedures o 33 operating procedures have changes and all 33 are scheduled to be revised prior to 05/01/88 or prior to the expiration of the change.
D. Casualty Procedures 1 i
o 10 casualty procedures have changes and all i 10 are scheduled to be revised prior to i 05/01/88 or prior to the expiration of the change.
E. Maintenance Procedures o Staff dedicated to incorporating changes 4 l o Total procedures with outstanding changes 118 4.- i.
. s 3 F. Maintenance Surveillance i
o 47 surveillances scheduled to be run betwesn t j 04/07/88 and 05/01/88
- o 16 of those 47 surveillances have changes o 16 revisions are in the process of being
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approved prior to their performance date or expiration date '
o 36 surveillances scheduled for performance after 05/01/88 will have revision completed :
5 days prior to their scheduled performance. :
i o 11 Electrical Maintenance procedures will be
- revised within 30. days of expiration of the '
change.
o 41 Instrument Maintenance procedures will be i
- revised within 30 days of expiration !
o 11 Mechanical procedures will be revised within j 30 days of expiration 2
o 2 Maintenance Administ?tative procedures will be revised within 30 days of expiration 2.2 Maintain daily status ,
, o on a daily basis changes issued in the previous
- 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are distributed to responsible groups
- to incorporate or coordinate with revision j schedules or performance schedules,.
- 2.3 Additional Management Controls o Document Control Procedures provide site-wide
- distribution of all temporary changes that are l approaching expiration, and notification of all expired changes. The responsible department has the responsibility to revise the procedure
- by incorprating the change if required.
! o The Procedure Development Project has delivered to each department procedure coordinator the list of temporary changes for incorporation as revisions where applicable.
i o Document Control Procedures provida daily status and tracking of all temporary changes.
- l j 3.0 Interim Migration Plan j Interim measures currently in progress include continuing the immediate action plan while expediting the development of the long term fix. Interin measures include: *
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o Continue methodology described in Section 2 above until the numbers of Temporary Change Notices are reduced to an acceptab.le level, i
j o A new Procedure Change Notice Program has been developed and is currently being reviewed by Rancho l Seco Management. Some key elements of the program which, when implemented, are expected to reduce the !
total number of Temporary Change Notices and to provide better control are as follows:
- 1. Implement a single method to make Temporary Changes. At present, there are three types to Temporary Changes (Procedure Temporary Change Notice, Procedure Interim Change Notice, Procedure change Notice). The new program provides for '
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- 2. Implement a single Procedure Action Request form for all procedure actions. At present there are three Temporary Change Notice forms and two i Procedure Request forms. The new program provides for gna.
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- 3. Implement a new process for Temporary Changes ;
which are to become permanent. At present, all change notices can become permanent and can stay i active for 90 days. The new program will require l Temporary Changes (that are designated to become permanent), be word processed into a revision at i
the end of the approval cycle (14 days). Those designated "Temporary" will expiro after 90 days.
- 4. The new program will require a Status Tracking System be implamented to appraise procedure owners of the Temporary Change Status of procedures they are responsible for and to provide visibility to management.
4 4.0 Long Term Action Plan o Implement long term procees improvements i o Continue with upgrade of all plant procedures to i eliminate need for "Change Notices".
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. o a N' ATTACHMENT VII GCA 88-258
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NRC The NRC Team observed that the current Rancho ,
1 Observation: Seco Technical Specifications do not address shunt
- trip feature of the current Reactor Trip Breaker.
l Rancho Seco As a result of NRC Generic Letter 83-28, automatic Responset actuation of the shunt trip attachment was installed and Proposed Amendment 114, to the Technical Specification was submitted to include ,
provisions for testing the shunt trip attachment !
and the Silicone controlled Rectifier (SCR) relays. The Proposed Amendment modifies the Rancho Seco Technical Specifications in accordance with the guidelines contained in NRC Generic Letter 85-10. Generic Letter 85-10 presents acceptable changes in the form of Model Standard
- Technical Specifications (STS). Previously, there were no requirements for testing the SCR relays; i therefore, the Model STS sections on SCR relays "
have been included in Proposed Amendment 114 to 4
the Rancho Seco Technical Specifications.
Although the NRC has not as yet, approved Proposed i
Amendment 114, Revision 1, Supplement 1, dated ,
December 9, 1986 (JEW 8 6-1986) , the shunt trip j devices installed in the Reactor Trip Breakers are tested under EM.170, CRD Breaker Preventive Maintenance. l 1
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..+e ATTACHMENT VIII GCA 88-258 NRC _The NRC Team observed instances of apparent observations inadequate seismic restraints or other measures to insure proper Storage control of 01mporary storage cabinets or other non-permanently Lttached hardware within the plant. ,
Rancho Seco other than containment, there is no formal Response procedure to address seismic storage controls.
The System Engineering Group has developed a System Progress Report Program to provide a documented means by_which the System Engineer maintains a knowledge of the status of his system and actively participates in the maintenance, testing, and operation of his system.
As part of the system assessment, a system Progress Report is prepared to document the material condition of the system and any required corrective actions. Corrective actions shall be initiated by an EAR, Work Request, PDQ, or other document. The System Engineers responsibility will encompass the control of non-seismically controlled equipment that could impact systems.
Since November 1987, Quality Assurance has been performing housekeeping surveillance activities in preparation for restart. The most recent inspection occurred on March 23, 1988, during which time the Nuclear Service Electrical Building and Auxiliary Building were walked down in accordance with AP.18, Plant Housekeeping and Inspections. Concerns similar to those of the NRC Team have been noted by Quelity and appropriate correct $ve actions generated.
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ATTACHMENT IX GCA 88-258 NRC The NRC questionod numerous members of the Observation: operating staff as to why the 'B' letdown cooler is out of service. There was no evidence of an overall understanding of that question.
Rancho Seco Operating personnel are aware of the operability Response: status of the 'B' letdown cooler. It is normally valved out by procedure.
The history of the 'B' letdown cooler being valved out is currently being investigated by System Engineering Department. In order to preclude any further confusion an entry was made in the Night Order Book giving the reason tha 'B' letdown cooler is valved out. This entry will address a suspected tube leak and provide guidance on maintaining the cooler in an "cut of service" condition.
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GCA 88-258 i
NRC The NRC is concerned that a Shift Supervisor Observation: Emergency Maintenance (SSEM) Work Request (WR141983) was issued for a trouble shooting condition. Specifically, an SSEM was-issued for the failed surveillance of the number 3 control Rod Drive (CRD) breaker.
Rancho Seco Quality Assurance recognized that the Response: generation of the subject SSEM was inappropriate and issued a "stop work" on the issuance of any future SSEM's. The critical losue wac that WR141983 did provide the instructions or controls necessary to prevent the loss of potentially significant investigative evidence, which may prevent the identification of the root cause.
Operations departrent and Quality Assurance are (jointly) revising RSAP 0803, Work Requests, in order to establish new criteria under which an SSEM can be issued and provide the administrative controls necessary to assure maintenance activities are performed in accordance with 10 CFR 50 Appendix B Criteria V, Instructions, Procedures, and Drawings, and Criteria XVI, Corrective Action requirements. The revision to RSAP 0803 is forecast to be revised by May 9, 1988.
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