NL-87-1411, Monthly Operating Rept for Oct 1987

Monthly Operating Rept for Oct 1987

ML20236V750
Person / Time
Site:	Rancho Seco
Issue date:	10/31/1987
From:	Bosakowski P, Karen Meyer SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
IEB-85-003, IEB-85-3, NL-87-1411, NUDOCS 8712070053
Download: ML20236V750 (13)

Text

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OCTOBER 1987 l

SUMMARY

OF PLANT OPERATIONS The plant was in cold shutdown for the entire month of October. The initial 1 shutdown was due to the December 26, 1985, loss of Integrated Control System l power event.

PERSONNEL CHANGES REQUIRING REPORT ,

l One personnel change is reportable pursuant to Technical Specification Figure 6.2-2 as revised in Proposed Amendment No. 138. Rancho Seco's new l Manager, Plant Performance Department, is Joe Flynn.

Mr. Flynn is an Institute of Nuclear Power Operations (INPO) employee and was most recently employed as Manager, Technical Development Department. He acquired 10 years experience as Operations and Maintenance Superintendent while employed at Consumers Power Co. and holds an SR0 License.

SUMMARY

OF CHANGES IN ACCORDANCE WITH 10 CFR 50.59 The plant staff accepted documentation packages in October 1987 for the facility changes described below which required detailed safety analyses. In addition, procedure changes from the last month are included. These changes were reviewed in accordance with the Technical Specifications by the Plant Review Committee (PRC) and the Management Safety Review Committee (MSRC).

There were no documentation packages completed for tests or experiments during October 1987.

1. The normal and alternate power supply sources for the CO2 System were changed from Class I ac/dc panels and MCCs to Class II ac/dc panels and MCCs. Three CO2 System power cables in Class I raceways were spared and abandoned in place; the other two associated cables were removed from Class I raceways. New cables were routed in non Class I raceways. Cable scheme numbers were changed, cable tags relabeled and the CRTS updated.

This change (ECN A-4382, Revision 1) does not compromise nuclear safety.

The margin of safety is insignificantly reduced by downgrading the CO2 power supply from Class I to Class II. Multiple failures of Class I systems would still have to occur before a fire could eliminate both trains of an essential safety system. (Log No. 731)

2. A deluge sprinkler system was added over the two AFH pumps (P-318 and P-319) located within the missile cage of the reactor yard area (Detector Zone 110). General work scope included verifying fire water availability, tie-in point to existing fire water mains, pipe routing and supports, sprinkler nozzles, spray shields to prevent ingestion of water, electrical power for deluge valve, and detectors with annunciation to the control room. Piping which is routed directly over pumps, motors, or controls is supported using II/I criteria. The electrical power supply to the deluge valve and detectors is from a system which is backed up in the event of an offsite power loss. Freeze protection was provided for all components normally containing water.

8712070053 871031 2 DR ADOCK 0500 A

This modification (ECN A-5530, Revision 2) improves plant safety an't reliability by mitigating the effects of a fire in the AFH pump area. ,

The sprinkler system will also prevent a fire at one pump from spreading i to the second pump. Addition of this system precludes the use of a continuous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> firewatch. Technical Specification 3.14 was revised (Amendment No. 85) to include this deluge system. (Log No. 585) j

3. The District completed the refurbishment of the following MOVs as part of ,

the MOV program performed in response to IE Bulletin 85-03.

ECN Number Valve Number /Acolicable System R-0968BF, Revision 0 HV-36050/ Auxiliary Steam (Log No. 849, Revision 2)

R-0914HO, Revision 0 SFV-23508/High Pressure Injection (Log No. 831 Revision 1)

The MOV program was outlined to the NRC in letters dated June 16 and November 5, 1986. The overall engineering package was implemented to prevent the valves from failing on demand in a common mode due to improper switch settings as described in IE Bulletin 85-03.

4. ECN R-0826, Revision 1, was in response to the December 26, 1985 loss of ICS power transient. The modification provides an automatic trip of ICS 24V dc power on loss of NNI X, Y or Z 24V dc buses or NNI X or Y 118V ac buses. The Rancho Seco Deterministic Failure Committee restart group determined the ICS should be tripped on loss of NNI X, Y or Z power and alternate indications and controls should be provided because the resulting failures are too complex to be able to attain good contiol of the plant. The change is an operational enhancement and will improve plant safety in response to a loss of ICS function and loss of most control room instrumentation.

The USAR will be revised to reflect the new trip mode of ICS on loss of NNI power. No Technical Specification changes are required for this modification. All equipment and power required for ECN R-0826 is Class 2.

(Log No. 815)

5. Cooling was required in order to maintain the environmental qualifications of safety related equipment in the Nuclear Service Electrical Building (NSEB). ECN A-4102, Revision 0, installed the HVAC system for the NSEB (both normal and essential). The building is divided into an "A" side and a "B" side. Separate ductwork, air handling units and condensing units were provided for each train. The system was procured and installed to appropriate codes and standards. The essential system is redundant and single failure proof. (Log No. 361, Revision 1)

. s* .

6. ECN R-1820, Revision 0, replaced the existing radiator yard equipment doors on the Diesel Generator Building with a removable steel plate tornado missile barrier. It also replaced the existing radiator yard personnel doors with a permanent steel plate tornado missile barrier.

Additionally, the ECN protected the diesel control room doors.in the '

Diesel Generator Building with a concrete tornado missile barrier.

This modification assures that the Design Basis Tornado missiles will not impact on, or that the barriers will not collapse onto, vital equipment.

. The possibility for an accident or malfunction of a different type than i any evaluated previously in the Safety Analysis Report will not be created because the modification changed the Diesel Generator Building to meet design commitments.

The margin of safety as defined in the basis for any Technical Specification was not reduced since this modification increased the ,

building's capability to withstand Design Basis Tornados to that required '

by design guides and commitments. (Log No. 1009)

7. ECN R-0770, Revision 0, replaced the turbocharger and spring drive gear on each Bruce-GM Emergency Diesel Generator (G-886A & G-8868) with upgraded components from the manufacturer.

The diesel subshaft and bracket assembly and No. 1 idler gear for each Bruce-GM diesel also were replaced with upgraded components from the manufacturer.

Since this modification was a replacement of parts only, the change will not lead to a failure which has not been previously analyzed. Redundancy of the diesels is maintained. A single failure can only disable one generator. (Log No. 804)

8. The updated Fire Hazards Analysis Report identified fire areas required by 10 CFR 50 Appendix R to have rated fire barriers. Thirty existing HVAC openings were identified: four do not contain rated fire dampers, four do not contain fire dampers, four require 3-hour rated fire damper upgrades due to high fire loadings or licensing commitments, and 18 are not installed per the manufacturer's installation instructions. l This change (ECN A-5767, Revision 1) added 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> U.L. rated fire dampers, replaced existing unacceptable fire dampers with 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> U.L. rated fire dampers, and moved / modified existing fire dampers to comply with U.L. and manufacturer's installation requirements, as required to meet 10 CFR 50 Appendix R requirements. Replacement / modification of mounting hardware was also done, as required.

A change or addition to Technical Specifications was not involved. This modification did not involve an unreviewed safety question or a change to the facility as described in the USAR. Nuclear safety was not affected. <

(Log No. 648)

9. ECN R-1028, Revision 1, installed a bar graph and digital meter on the HISS console to indicate the heatup/cooldown rate of the Reactor Coolant System (RCS). Rate of change is calculated by IDADS using T-cold inputs from TE-21025C and TE-21024C (installed by ECN R-0953). This modification included the installation of a bar graph / digital indicator on control room console HISS and the cable installation between the IDADS computer cabinet i and console H1SS. All equipment installed is QA Class II. l This modification provides the control room with the heatup/cooldown rato )

of. the RCS during normal heatup, cooldown, trip, and/or a transient. The  ;

installation of heatup/cooldown indication in the control room is an operational enhancement which will assist the control room operators in determining and maintaining compliance with Technical Specifications.

The probability of occurrence or consequences of an accident or malfunction previously evaluated will not increase since this change does '

not affect any equipment important to safety.

The possibility of a malfunction not previously analyzed will not be created since IDADS is a non-safety system. The margin for safety as addressed in Technical Specifications will not be decreased since IDADS is not included in Technical Specifications; therefore, this modification does not involve an unreviewed safety question. (Log No. 924)

10. Both NSEB Essential HVAC System Condensing Units, U-503A and U-503B, were modified to provide cyclic operation of the condenser cooling fans as a function of the outdoor ambient temperature. Controls were provided to cycle two of the three condenser cooling fans of each unit, on or off, in sequence, at predetermined temperature setpoints. A combination temperature element, temperature transmitter, and temperature switch for each unit were provided to accomplish the cycling control.

This facility change (ECN R-1026, Revision 0) is an operational enhancement to the NSEB Essential HVAC System. The modifications provide for cyclic operation of the condenser cooling fans to more appropriately respond to the low end of the outdoor ambient temperature range. This is not a change to the facility as described in the USAR. A change or addition to Technical Specifications is not required. This modification is bounded by the Licensing Design Basis. An unreviewed safety question is not involved. (Log No. 886)

11. ECN R-1023B, Revision 2, modified the Essential Refrigeration Pumpdown Control to provide automatic pumpdown control. Without automatic pumpdown, liquid refrigerant collected in the oil separator when the system was shut down.

The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the Safety Analysis Report will not be increased because this modification improves the flexibility of the NEH System and eliminates failure modes in the installed system without creating new ones.

I

The margin of safety as defined in the basis for any Technical Specification wi.ll not be decreased because the change improves the control but does not affect the design function of the NEH. (Log

, No. 9928)

12. The NSCH and the CCH piping was checked for wall' thickness to ensL e it met seismic. criteria. Coating was then applied to the piping, valves, and flanges (ECN A-3299, Revision 0).

The coating ' system is qualified for DBA conditions. .The coating system does not pose any safety related problems for a safe shutdown of the plant or interfere with the safe operation of the plant. Limited abrasive blasting was only done with vacuum blasting under complete enclosures with HEPA filtering. The evaporation of the radioactive residual was tested and only discharged through the controlled and monitored Reactor Building ventilation system. The vapor was not detrimental to the ventilation system.

The change will not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the USAR, or create the possibility of an accident or malfunction of a different type than any evaluated previously in the USAR.- The margin of safety as defined in the basis for any Technical Specification was not reduced. An unreviewed safety question was not involved. (Log No. 205, Revision 1)

13. This modification (ECN R-1195A, Revision 0) replaced the butt-welded motor operated isolation gate valve HV-26511 with a motor operated socket welded

-isolation globe valve and a new socket welded, manually operated globe valve. It included disconnection of wires from the existing M0V and reconnection to the new valve operator. All I&C and electrical cabling required no change.

The new manually operated isolation valve is a 1" 1,500 lb. butt-welded globe valve and was added upstream of the motor-operated isolation valve on line 60485-1"-ED between the 2" x 1" reducer on line 60487-2"-E0 and the motor operated isolation valve to facilitate the maintenance of the motor operated isolation valve.

l This change is an operational enhancement only. It provided for the l repair 'of a damaged valve and added a normally open manual isolation valve to facilitate the maintenance of the motor operated isolation valve without affecting the system failure modes. j Implementation of this modification does not involve an unreviewed safety question. (Log No. 901, Revision 2) t

l MAJOR SAFETY-RELATED MAINTENANCE TESTS AND MODIFICATIONS NOT REQUIRING f 1

DETAILED SAFETY ANALYSES The District completed the Emergency Feedwater Initiation and Control 1.

] (EFIC) System Cold Functional Test.

2. All 170 MOVs tested are engineering complete.

3. The District completed the Purification and Letdown System (PLS)

Interlock Test.

4. All 622 inspections conducted as part of the Cable Raceway Tracking System program are complete.

5. ECN A-3285, Revision 4, removed installed piping from downstream of valve i NGS-549 in the Nitrogen Gas System to the existing valve IAS-777 in the j Instrument Air System (IAS) and reinstalled PI-91503 directly downstream of IAS-777. This modification removed a cross-tie to the IAS.

6. ECN R-0587, Revision 1, provided configuration changes in SFAS relay cabinet H4SDB-00,

7. ECN A-4102B, Revision 0, installed normal HVAC units and Battery Room exhaust fans for the Nuclear Service Electrical Building (NSEB).

8. ECN R-1035, Revision 1, relocated thermocouple /pipewell assembly from supply air duct to return air duct. This relocation provides temperature control signals to the cooling coils of Essential Air Handling Units (AHUs) that represent average temperature of the rooms in the NSEB.

9. ECN R-1407, Revision 1, corrected a terminal post seal problem which was causing electrolyte leakage. Seals were reworked or cells replaced as necessary on affected batteries.

10. ECN A-3806, Revision 0, provided PA speakers for the East and Hest Spray Pond areas to make areas audible for purposes of evacuation instructions.

11. ECN A-4703, Revision 0, replaced chart recorder CJR-32 (located in panel H2CH) with a new recorder. The installation of a new recorder was necessary because of incorrect readouts and high maintenance costs.

12. ECN R-1081, Revision 1, corrected a design deficiency in flow control circuits for SF-A-7A and SF-A-78. High flow switches FSH-54701 and FSH-54702 in Rochester cabinets H4SCA and H4SCB, and analog IDADS inputs F-2900 and F-2902 in multiplexer cabinets H4CDAR7 and H4CDAR9 were removed from input loops of Foxboro I/E converters FY-54701A and FY-54702A, respectively.

Replacement of Rochester Instrument System's FSH-54701 and FSH-54702 were made with Foxboro's FSH-54701 and FSH-54702, and Foxboro's interposing relays FSHX-54701 and FSHX-54702 were located in existing Spec 200 enclosures on the Auxiliary Building roof.

13. ECN R-0113, Revision 0, changed out junction box H75087 to allow a larger terminal board to be installed, thus avoiding having three lugs under one screw. This ECN also documented the wiring to H9H19 on the wiring diagrams, i

14. ECN R-0027, Revision 0, removed existing splice plates connecting the main bus in S3A to the incoming feeder bus and installed new qualified splice plates.

15. ECN R-0821 Revision 0, installed IDAD inputs for ICS, NNI, ABT status monitoring. This modification provides indication of which inverter is supplying the power (normal or standby) and loss of any power supply.

16. ECN R-1785, Revision 0, rerouted the instrumentation cables associated with DHS cross-tie flow transmitters FT-26048 and FT-26049.

17. ECN R-2276, Revision 1, replaced power cables for the Nuclear Service Raw Hater (NSRH) pump motor for P-472A with new Class I cables.

18. ECN R-0775B, Revision 0, provided for excavation required for the new sump (including backfill and repaving, as required), and ECN R-0775C, Revision 1, provided the foundations for the new RHUT.

19. ECN A-3795A, Revision 3, replaced the existing NSRH side makeup pump lube oil cooler with a stainless steel heat exchanger.

20. ECN A-3795C, Revision 1, and ECN A-3795E, Revision 3, replaced the existing NSRH side high-pressure injection pump lube oil coolers (E-239C & D) with stainless steel exchangers.

21. ECN R-1023, Revision 0, modified the NSEB Essential HVAC. In order to implement a systems approach, the sub-ECNs described below were used to install and coordinate the control of the entire HVAC System.

ECN R-1023A, Revision 0, removed and capped hot gas bypass connections to upper cooling coil sections of Essential AHus.

ECN R-1023C, Revision 0, provided contr01 of the loading and unloading of refrigeration compressor cylinders from system suction pressure. This modification enables Essential Refrigeration Condensing units to follow the cooling load presented by the evaporators of the Essential AHUs.

ECN R-1023D, Revision 0, modified the control sequence of the four cooling coil sections in order to provide closer incremental control of supply air and enable the Essential AHUs to follow internal load variations in the NSEB.

22. The District completed the refurbishment of the following MOVs as part of the M0V program performed in response to IE Bulletin 85-03.

ECN Number Valve Number /Acolicable System i

R-0976B, Revision 0 HV-20584/ Gland Steam & Condensate R-0976G, Revision 0 HV-35033/ Main Condensate & Makeup R-0976H, Revision 0 HV-35034/ Main Condensate & Makeup R-0976M, Revision 1 FV-33011C/ Main Condensate & Makeup R-0976P, Revision 1 FV-33011E/ Main Condensate & Makeup R-0976T, Revision 1 FV-33011J/ Main Condensate & Makeup R-0976Y, Revision 1 FV-33012E/ Main Condensate & Makeup R-0976AP, Revision 0 HV-29108/ Pressurizer Relief Tank R-0976BE, Revision 0 HV-43504/ Site Reservoir R-0976BG, Revision 0 HV-43606/ Site Reservoir R-0976BH, Revision 0 HV-43607/ Site Reservoir R-0976BN, Revision 0 HV-52017/HVAC R-0976BP, Revision 0 HV-52018/HVAC

L '. . . ... c.

i lELING INFORMATION REQUEST..

1. Name of Facility Rancho Seco Unit 1

2. Scheduled-date for next refueling shutdown: Seotember 15. 1988 i

3. Scheduled date for restart following refueling: January 15. 1989

4. Technical Specification change or other license amendment required:

l a) Change to Rod Index vs Power Level Curve (TS 3.5.2) i.

b) Change to-Core Imbalance vs Power-Level Curve (TS 3.5.2) c) -Tilt Limits (TS 3.5.2)

5. Scheduled.date(s) for submitting proposed licensing action: March 15. 1988 Important licensing considerations associated with refueling:

6. N/A

7. Number of. fuel ~ assemblies.:

-a)- In the core: 177 b)_ In the Spent Fuel Pool: 316

8. ,Present licensed spent fuel capacity: 1080

9. Projected date of the last refueling that can be discharged to the Spent Fuel Pool: December 3. 2001 1

1 1

l

' AVERAGE DAILY UNIT P0HER LEVEL-DOCKET NO. 312

-UNIT Rancho Seco Unit 1 DATE 10/31/87-COMPLETED BY P. Bosakowski TELEPHONE (916) 452-3211 MONTH October 1987 DAY' AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 0 0 7 23 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0 INSTRUCTIONS l- On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

I l

OPERATING DATA REPORT DOCKET NO. 50-312 DATE 10/31/87 COMPLETED BY P. Bosakowski TELEPHONE (916) 452-3211 OPERATING STATUS

1. Unit Name: Rancho Seco Unit 1 Notes:

2. Reporting Period: October 1987

3. Licensed Thermal Power (MHt): 2.772

• Error corrected

4. Nameplate Rating (Gross MWe): 963 from previous

'5. Design Electrical Rating (Net MWe): 918 report.

6. Maximum Dependable Capacity (Gross MHe): 917

7. Maximum Dependable Capacity (Net MWe): 873

8. If changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: N/A

9. Power Level to Which Restricted, If Any (Net MHe): 0

10. Reasons For Restrictions, If Any: NRC letter dated 12/26/85 This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744 7.296* 109.920*

12. Number of Hours Reactor Has Critical 0 0 54.322

13. Reactor Reserve Shutdown Hours 0 0 10.300.2

14. Hours Generator On-Line 0 0 50.363.8

15. Unit Reserve Shutdown Hours 0 0 1.210.2

16. Gross Thermal Energy Generated (MHH) 0 0 127.861.688__

17. Gross Electrical Energy Generated (MHH) 0 0 41.523.197

18. Net Electrical Energy Generated (MHH) -4.422 -42.747 38.246.038

19. Unit Service Factor 0.0% 0.0% 45.8%

20. Unit Availability Factor 0.0% 0.0% 46.9%

21. Unit Capacity Factor (Using MDC Net) 0.0% 0.0% 39.9%

22. Unit Capacity Factor (Using DER Net) 0.0% 0.0% 37.9%

23. Unit Forced Outage Rate 100.0% 100.0% 42.5%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

N/A

25. If Shut Down At End Of Report Period, Estimated Date of Startup: Indefinite

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A

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• SACRAMENTO MUNICIPAL UTILITY DISTRICT C P, O. Box 15830, SacramEb3 C4pg852-1830, (916) 452 3211 AN ELECTRIC SYSTEM SERVI $G THE F#y[J CALIFORNIA p"'..

NL'87-1411 'Q November 13, 1987 U. S. Nuclear Regulatory Commission Attn: J. B. Martin, Regional Administrator Region V Office of Inspection and Enforcement 1450 Maria Lane, Suite 210 Halnut Creek, CA 94596 DOCKET NO. 50-312

, RANCHO SECO NUCLEAR. GENERATING STATION

! LICENSE NO. DPR-54 OPERATING PLANT STATUS REPORT

Dear Mr. Martin:

Enclosed is the October 1987 Monthly Operating Plant Status Report for tha Rancho Seco Nuclear Generating Station. The District submits this report pursuant to Technical Specification 6.9.3.

Sincerely,

/

Karl A. Meyer Manager, Nuclea Licensing Enci (5)

{

cc: I&E Hash (12)

F. J. Miraglia, NRR, Bethesda MIPC (2) I INP0 G. Kalman R. Twilley, Jr.

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RANCHO SECO NUCLEAR GENERATING STATloN O 1444o Twin Cities Road, Herald, CA 95638 9799: (2o9) 333 2935 [bM