ML20248C430

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Annual Rept, Covering Period 970507-980506
ML20248C430
Person / Time
Site: Rancho Seco
Issue date: 05/06/1998
From: Redeker S
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To: Weiss S
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MPC&D-98-084, MPC&D-98-84, NUDOCS 9806020150
Download: ML20248C430 (12)
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SACRAMENTO MUNICIPAL UTlWTY DISTRICT C P. O. Box 15830, Sacramento CA 95852-1830, (916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA MPC&D 98-084 May 27, 1998 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Docket No. 50-312 Rancho Seco Nuclear Station License No. DPR-54 RANCIIO SECO ANNUAL REPORT Attention: Seymour Weiss The District submits the Rancho Seco Annual Report in accordance with Rancho Seco Permanently Defueled Technical Specifications (PDTS) D6.9.4 and D6.9.6b, and 10 CFR 50.59(b)(2). The enclosed report contains (1) shutdown statistics, (2) a narrative summary of shutdown experience, (3) Environmental Report information, and (4) tabulations of facility changes, tests, and experiments required pursuant to 10 CFR 50.59(b).

The enclosed report covers the period May 7,1997, through May 6,1998. The NRC approved the original PDTS, which included the current Rancho Seco Annual Report requirement,'in April 1992, and the District implemented the PDTS on May 7,1992. Prior to May 1992, Rancho Seco submitted monthly reports in accordance with the Operating Plant Technical Specifications.

Members of your staff requiring additional information or clarification may contact Jerry Delezenski at (916) 452-3211, extension 4914.

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k teve J. Redeker Manager

}j f Plant Closum & Decommissioning Enclosum

, , s. V U c0 cc w/ Encl: E. W. Merschoff, NRC, Arlington, Texas R. Dudley, NRC, Rockville

! 9906020150 990506 i PDR ADOCK 05000312

! R PM RANCHO SECO Nt4 LEAR GENERATING STATION O 14440 Twin Cities Road. Herald, CA 95638-9799; (209) 333-2935 l

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Page 1 of 11 RANCllO SECO ANNUAL REPORT Shutdown Statistics:

The District provides the following shutdown statistics:

1. Rancho Seco permanently shut down nuclear power operations on June 7,1989.
2. The Rancho Seco reactor has been completely defueled since December 8,1989.
3. The Rancho Seco Spent Fuel Pool (SFP) contains 493 spent fuel assemblics and is licensed for 1080 spent fuel assemblies.
4. The NRC amended the Rancho Seco operating license to Possession-Only status on March 17,1992.
5. The NRC issued Rancho Seco a Decommissioning Order on March 20,1995. The Order (1) authorized the District to decommissioning Rancho Seco and (2) accepted the Rancho Seco Decommissioning Funding Plan.
6. The District revised the NRC-approved Rancho Seco Decommissioning Plan (which became the Post Shutdown Decommissioning Activities Report (PSDAR) pursuant to revised 10 CFR 50.82)in March 1997, to (1) conform to the new 10 CFR 50.82 PSDAR content requirements and (2) address immediate incremental decommissioning activities.
7. Rancho Seco has been in the Permanently Defueled Mode (PDM) during the entire reporting period (May 7,1997, through May 6,1998).
8. In November 1997, the District took the Component Cooling Water (CCW) System out of service for approximately one week to support the CCW surge tank replacement modification. The CCW system is a suppon system for the Spent Fuel Cooling system.

During the approximately one week CCW system outage, the Spent Fuel Pool (SFP) water temperature increased from 70 F to 86 "F.

The SFP leak rate through the leak chase system was monitored during the CCW System outage. The leakage held steady at approximately 33 gallons per day. This leak rate is consistent with the normal, steady state leak rate, which typically runs between 30 and 33 gallons per day.

9. The District intends to remove all the spent fuel assemblies from the SFP starting in 1999, and place the fuel in dry storage at the Rancho Seco Independent Spent Fuel Storage Installation (ISFSI) being licensed pursuant to 10 CFR 72. The District then intends to drain and process the SFP water following spent fuel assembly removal.

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Page 2 of 11 RANCllO SECO ANNUAL REPORT Shutdown Experience Summary:

The District provides the following shutdown experience summary.

General Plant Administrative Activities

1. The District continues to implement its Incremental Decommissioning Action Man, which defines the near-term program for removing and dismantling both non and low level radioactive systems and equipment.
2. The District continues to pursue Independent Spent Fuel Storage Installation (ISFSI) license approval. Also, Rancho Seco continues to safely store its spent nuclear fuel in the SFP.
3. Special Nuclear Materials coordinators completed the annual Special Nuclear Materials inventory and Semi-annual Special Nuclear Materials Accountability reports. f

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4. Technical Services developed and completed the Rancho Seco Hardened SAFSTOR )

Transition Plan.

5. Plant personnel completed the annual Rancho Seco medical drill, fire drill, and emergency exercise.
6. The District issued a contract to Hake Associates and GTS/Duratek for decontamination i services
7. Plant management commissioned an Employee Action Team to evaluate and recommend improvements for processing material generated from incremental decommissioning activities.
8. Technical Services issued nine Incremental Decommissioning Packages in accordance with the Incremental Decommissioning Action Plan, the Post Shutdown Decommissioning Activities Report, and plant administrative procedure RSAP-1900,

" Incremental Decommissioning Control."

9. Technical Services initiated seven Design Change Packages to isolate portions of operating plant systems that are no longer required to function and make these isolated ponions of systems available for incremental decommissioning.

l 10. Operations developed and completed the Hardened SAFSTOR equipment list.

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Page 3 of 11 RANCilO SECO ANNUAL REPORT General Plant Administrative Activities (Continued) l

11. Operations completed Red Cross First Responder training for 20 Operators and 12 j additional Rancho Seco employees.
12. The District issued a radioactive waste disposal contract to Envirocare of Utah.
13. Operations completed developing the Special Test Procedure and Operating Procedure for the new Plant Integrated Computer System (PICS).

Fuel Off-load Proicct Activities

1. Maintenance completed fabrication and installation of the safety hand rails in the Fuel Storage Building, installed the spent fuel pool stop log, removed upender pit grating, removed hydraulic tubing lines, and removed upender basket hydraulic rams to suppon Impact Limiterinstallation;
2. Rancho Seco personnel completed weld inspections on the Horizontal Storage Modules at the ISFSI;
3. Maintenance installed additional Gantry Crane surge protectors to support continued.

Gantry Crane testing; and

4. Maintenance repaired the Gantry Crane to correct a blown fuse problem that resulted in the loss of main and auxiliary hook control.

Incremental Decommissioning Team Activities:

J The Incremental Decommissioning Team (IDT) dismantled the following systems and major  ;

secondary plant components:

1. ' Turbine Plant Sampling System
2. I Portions of the Demineralized Water System, Instrument and Service Air Systems, Carbon Dioxide System, Service Water System, Turbine Plant Cooling Water System, Secondary Chemical Addition System, Gland Steam and Condenser System, Auxiliary j Steam System. Heater, Drain and Vents System, Main Condensate and Make-up System,  ;

Fire Protection System, and 480 Volt AC System in the Turbine Building

3. The small auxiliary boiler and large auxiliary boiler i

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l Page 4 of 11 RANCilO SECO ANNUAL REPORT Incremental Decommissioning Team Activities: (Continued)

4. The 'A' and 'B' Sixth Point Drain Coolers
5. Air Ejector System
6. Main Feed Water Pumps
7. Turbine Lube Oil Reservoir and Coolers
8. . liigh and Low Pressure Steam Turbine enclosures on the Turbine Deck
9. Four Moisture Separator Reheaters l
10. Main Feed Water Pump Lube Oil Reservoirs 1
11. The 'A' and 'B' Third and Fourth Point Feed Water Heaters Additional Incremental Decommissioning related activities include the following:
1. Asbestos contractors removed a little more than one-half million pounds of asbestos containing material in support of incremental decommissioning activities.
2. Incremental Decommissioning Team (IDT) personnel segmented the Moisture Separator Reheaters (MSRs), decontaminated various external MSR components, and packaged five segmented MSR tube bundles for eventual shipment to a low level radioactive waste disposal facility.
3. IDT personnel made 49 shipments totaling approximately 370 tons of scrap metal to the District's metal recyc!e contractor.
4. IDT personnel made four shipments totaling approximately 62.5 tons of low level radioactive decommissioning waste to Hake Associates for decontamination and disposal.
5. IDT personnel isolated the Plant Cooling Water System and Condensate Storage Tank from the Turbine Building to support incremental decommissioning work.
6. Maintenance personnel completed a CO2 system modification to support incremental decommissioning activities in the Turbine Building.

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Page 5 of 11 RANCIIO SECO ANNUAL REPORT

7. Maintenance personnel completed modification that supponed the removal of Plant Air Compressor C-900B.
8. Maintenance personnel isolated portions of the fire protection system in the Turbine Building to support incremental decommissioning activities 9.- Maintenance and contract personnel replaced the CCW surge tank and removed equipment from The Auxiliary Building roof to support incremental decommissioning.
10. Maintenance and contract personnel electrically isolated and dismantled the 60-meter meteorological tower.

General Plant Maintenance Activities:

The Rancho Seco Maintenance Department performed the following significant maintenance activities:

1. Repaired diesel fire pump P-996;
2. Repaired several fire hydrants that had degraded water flow;
3. Replaced a faulted 'B' phase conductor cable associated with CCW pump P-462B;
4. Performed annual and quarterly inspections on the Gantry, Cask Suppon Facility, and Interim On-site Storage Building cranes, and fuel handling bridge, including load testing, as required;  ;

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5. Repaired the Folsom South Canal pumping station 48 Volt DC battery charger and installed new batteries; i
6. Repaired an oil leak on CCW pump P-462A; l
7. Completed 'C' main air compressor and fire system valves preventive maintenance;
8. Completed preventive maintenance on spent fuel pool cooling pump P-272; )

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9. Refurbished and re-installed one Folsom South Canal pumping station 4.16 kV circuit I

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P Page 6 of 11 RANCIIO SECO ANNUAL REPORT 1

General Plant Maintenance Activities:(Continued)

10. Replaced cast cooling tower aviation lights and missing cooling tower ladder hold down clips; and
11. Successfully completed the diesel fire pump flow test surveillance.

Plant Modifications Maintenance completed the following plant Modifications:

1. Consolidated the 125 Volt DC and 120 Volt AC system loads
2. Installed and tested new plant effluent flow recorder FIRQ-95108
3. Replaced the CCW Surge Tank with the Chilled Water Storage Tank
4. Isolated the 'A' Spent Regenerant Tank Environmental Report Information:

In accordance with PDTS D6.9.6b, Rancho Seco is required to provide copies of (1) new permit and certificate applications and (2) permit and certificate changes or additions that are required by government agencies for protection of the environment to the NRC. During the reporting period, Rancho Seco did noi apply for any new permits or certificates, or receive any permit or certificate changes or additions required by a government agency for protection of the environment.

10 CFR 50.59(h) Summary:

The following is a tabulation of the facility changes, tests, and experiments that (1) occurred from May 7,1997, through May 6,1998, and (2) required a 10 CFR 50.59 safety evaluation.

None of the following changes evaluated in accordance with 10 CFR 50.59 resulted in an Unreviewed Safety Question.

g Page 7 of 11 RANCHO SECO ANNUAL REPORT 10 CFR 50.59th) Summary: (Continued) 1997 Rancho Seco Decommissioning Cost Update Report, July 1997, updated the cost estimate for decommissioning the Rancho Seco nuclear facility. The new cost estimate is $452.2 million. This updated cost estimate requires a change to the decommissioning cost information contained in the Post Shutdown Decommissioning Activities Report (PSDAR), Amendment 1 (Section 3.5 and 3.6). The PSDAR is a LBD, but the updated cost estimate does not require a change to any other LBD.

Design Change Package (DCP) R94-0002, Revision 2, " Plant Integrated Computer System," combines the functions of the IDADS, Bailey, and DRMS computers and annunciator window systems into a Personal Computer based plant computer system. This modification will not change the type or amount ofinformation that is available to operators in the control room.

This design change will require extensive changes to DSAR Chapter 7 and a change to Section 2 of the Decommissioning Fire Protection Plan (DFPP). The DSAR and DFPP are LBDs, but this design change does not require a change to any other LBD.

DCP R97-0018, Revision 0, " Isolate Plant Cooling Water (PCW) System from the Turbine Building," isolates the portion of the PCW system that serves the Turbine Building to facilitate incremental decommissioning activities in the Turbine Building. PCW is not required to provide cooling water to any plant equipment in the Turbine Building during the Permanently Defueled Mode. This design change will require a change to the DSAR (PCW Figure 9.2-4), which is a LBD, but will not require a change to any other LBD.

DCP R97-0022, Revision 0, " Component Cooling Water (CCW) System Surge Tank Replacement," replaces the CCW surge tank V-464 with Chilled Water Storage Tank T-771 to facilitate incremental decommissioning activities on the Auxiliary Building roof. This design change will require a change to the DSAR (Section 9.2.3.1), which is a LBD, to reDect local CCW Surge Tank level determination and elimination of level display and high or low level annunciation in the Control Room. This change does not require a change to any other LBD.

DCP R97-0025, Revision 0, " Isolate Turbine Plant Cooling Water (TCW) System from the

'B' Service Air Compressor and Aftercooler," isolates and the TCW system from the 'B' Service Air Compressor and Aftercooler, which are out of service and not required to function during the Permanently Defueled Mode. This equipment is being isolated to make it available for incremental decommissioning. This design change will require a change to the DSAR (Figure 9.2-6), which is a LBD, but will not require a change to any other LBD.

Page 8 of 11 RANCIIO SECO ANNUAL REPORT 10 CFR 50.59(h) Summary: (Continued)

Deviation from Quality (DQ) 93-0026, "Regenerant iloid Up Tanks 'A' Liner Leak,"

Disposition, Revision 1, identified that both the 'A' and 'B' RHUT liners leaked and recommended that the B RHUT be relined with epoxy and the A RHUT be placed in standby.

Since the DSAR states that the 'A' and 'B' RHUTs have plastic liners, relining the 'B' RHUT with epoxy requires a change to the DSAR (Section 11.2.3.2 and Table 11.2-1). The epoxy continues to provide chemical resistance and does not change the 'B' RHUT characteristics.

Therefore, the DQ Disposition requires a change to the DS AR, which is a LBD, but does not affect any other LBD.

Incremental Decommissioning Package IDP-0009, Revision 0," Removal of Equipment from Auxiliary Building Roof," removes equipment not required to function in the Permanently Defueled Mode from the Auxiliary Building roof. The 10 CFR 50.59 evaluation forIDP-0009 identified DS AR information that should have been previously removed per the 10 CFR 50.59 evaluations that justified removing the Nuclear Service Cooling Water and Raw Water systems from service in late 1992. The 10 CFR 50.59 evaluation for IDP-0009 requires a change to the DSAR (Section 5.5.1), which is a LBD, but will not require a change to any other LBD.

Procedure CAP-0002, Revision 9, Temporary Change TC-01,"Off-site Dose Calculation Manual (ODCM)," changed the default flow rate used for normal gaseous effluent dose calculations for releases through the Auxiliary Building Stack from 47,740 CFM to 90,000 CFM.

This change (1)is based on recent Auxiliary Building Stack flow surveillance results, and (2) ensures continued conservative reporting of normal gaseous effluent dose. This temporary l procedure change was made permanent and directly affected the ODCM, which is a LBD, but did not affect any other LBD.

l Procedure RP.312.I.05, Revision 5, " Dosimetry Visitor Monitoring," removed the redundant dosimeter requirement for visitors accessing the street clothes areas of Radiological Controlled Areas (RCAs). Radiation workers with the necessary and required dosimetry escort visitors in RCA street clothes areas. A TLD is issued to visitors for entry beyond a step-off pad in a RCA. 3 This procedure change requires a change to the DSAR (Section 11.9.1), which is a LBD, but does j not require a change to any other LBD.

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P""" 9 8I 13 RANCHO SECO ANNUAL REPORT 10 CFR 50.59(b) Summary: (Continued)

Procedure RSAP-1900, Revision 1," Incremental Decommissioning Control," addressed proper review of Incremental Decommissioning Package revisions, including ALARA evaluation requirements. As a result of the 10 CFR 50.59 review associated with this change, plant management determined the statements in DSAR Section 11.6.2 were excessively prescriptive concerning ALARA evaluation documentation. DSAR Section 11.6.2 is simplified to require an ALARA evaluation that is described in general terms for each plant modification or design change rather than prescribing a specific type of ALARA evaluation using specific forms. This procedure change requires a change to the DS AR (Section 11.6.2), which is a LBD, but does not require a change to any other LBD.

Procedure SP.357, Revision 8," Quarterly Water Flow Alarm Device Functional Test,"

deleted water flow alarm testing for Fire Zones 40 and 41 because the location of the test valve presents a safety hazard for personnel performing the test. Also, the diesel generators and associated equipment that were located in these fire zones were previously removed. Currently, 3 the combustible loading in these rooms is minimal. The rooms are now used for storing metal scaffolding and metal ladders. This procedure change requires a change to Table 3-1 in the Decommissioning Fire Protection Plan (DFPP), which is a LBD, but does not require a change to any other LBD.

Procedure SP.641, Revision 0, Temporary Change TC-01," Auxiliary Hullding Grade Level Exhaust Air Filter System," addressed installing a hand loader to control damper PDV-54606 during this air filter test and removing the hand loader following completion of the test. This temporary procedure change was not made permanent. This temporary change is contrary to descriptions in DSAR Section 9.5.2.2.8 and Figure 9.5-7, but, since the change will not be made permanent, no DSAR change is required. This temporary procedure change is not contrary to any  :

other LBD.

1 Radiological Environmental Monitoring Program (REMP) Manual, Revision 10, editorially I changed the number of monthly water composite samples listed in REMP Manual Table I from one to two. The actual number of samples collected is two in accordance with the sample l locations specified in REMP Manual Table 6. This administrative change provides additional assurance the Rancho Seco REMP will continue to represent an environmental sampling program that meets the intent of applicable regulatory guidance and provide for accurate assessment of the radiological environment in and around the Rancho Seco site. This change directly affected the l REMP Manual, which is a LBD, but does not affect any other LBD. i 1

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Page 10 of 11 RANCllO SECO ANNUAL REPORT 10 CFR 50.59(h) Summary: (Continued)

Ran'cho Seco Quality Manual,Section XVIII, Revision 8, " Quality Assurance Program,"

made an editorial change to the wording in step 6.lj so that it is identical to the wording in PDTS D6.5.4j. This Rancho Seco Quality Manual change did not reduce the commitments in the Quality Assurance Program and did not require NRC approval prior to implementation. The change directly affected the Rancho Seco Quality Manual, which is a LBD, and did not affect any other LBD.

Rancho Seco Physical Security Plan, Revision 7, and Security Training and Qualification Plan, Revision 4, re-assigns most Security Program responsibilities from the Manager, Plant Closure & Decommissioning (Plant Manager) to the Manager, General Services. The Physical Security Plan retained the Plant Manager related Security responsibilities specified in the PDTS.

- Also, the Rancho Seco Supervisor, Security Operations duties and responsibilities are transferred to the General Services Supervisor, Security Operations. The Security chain of command on shift is unchanged and the Security shift responsibilities, procedures, and staffing levels are unchanged. Therefore, these administrative Security Program changes do not reduce the effectiveness of the Physical Security Plan and do not require NRC approval prior to implementation. These changes directly affect the Physical Security Plan and the Security Training and QualiGcation Plan and require changes to the DSAR (Section 12.1.2.lc and Figure 12.1-1), which are LBDs, but do not affect any other LBD.

l Special Test Procedure STP-1339, Revision 1, " Plant Integrated Computer S3 stem (PICS) )

Test," demonstrates the ability of PICS to monitor defueled plant operating parameters and provide necessary information and alarms to plant operators. This test is not described in the DSAR, but does nnt constitute an Unreviewed Safety Question because this STP is a functional ted designed to place new plant equipment into service. This STP does not require a change to any LBD.

Special Test Procedure STP-1339, Revision 2, " Plant Integrated Computer System (PICS)

Test," incorporates a change to the PICS modiGeation package DCP R94-0002 that adds an A/B switch for field inputs. This STP demonstrates the ability of PICS to monitor defueled plant .

I operating parameters and provide necessary information and alarms to plant operators. This test is not described in the DSAR, but does nol constitute an Unreviewed Safety Question because this STP is a functional test designed to place new plant equipment into service. This STP does not require a change to any LBD.  !

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1 l Page 11 of 11 RANCllO SECO ANNUAL REPORT 10 CFR 50.59(h) Summary: (Continued)

Special Test Procedure STP-1339, Revision 2, Temporary Change TC-01, " Plant Integrated Computer System (PICS) Test," permits proper testing of analog setpoints and deletes testing in simulate mode. This STP demonstrates the ability of PICS to monitor defueled plant operating parameters and provide necessary information and alarms to plant operators. The temporary change is to be made permanent. This test is not described in the DSAR, but does not constitute an Unreviewed Safety Question because this STP is a functional test designed to place new plant equipment into service. This STP does not require a change to any LBD.

Temporary Modification 97-04, Revision 0," Disconnect De-energized Equipment and Unused Connected Equipment to Accommodate PM on Nuclear Service Transformer without Taking down Start-Up Transformer No.1," disconnects Start-up Transformer X976 links to the 6.9 kV buses (RCP power) and the primary and secondary links of Nuclear Service Transformer X74. This temporary modification was made to accommodate performing preventive electrical maintenance on Nuclear Service Transformer X74 without taking down Start-Up Transformer No.1. This temporary modification is contrary to the configuration depicted in DS AR Figure 8.2-2, but, since the change will not be made permanent, no DSAR change is required. This temporary modification is not contrary to any other LBD.

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