ML18096A783

Monthly Operating Rept for May 1992 for Salem Unit 1.W/ 920612 Ltr

ML18096A783
Person / Time
Site:	Salem
Issue date:	05/31/1992
From:	Shedlock M, Vondra C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9206230070
Download: ML18096A783 (15)

Text

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• Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station June 12, 1992 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original copy of the monthly operating reports for the month of May 1992 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance 10CFR50.59 Evaluations Operating Summary Refueling Information General Manager -

Salem Operations RH:pc cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-l-7.R4 The_ Eni::!rnv_t=>Annlt:> __ _

--- --9206230070 920531 PDR ADOCK 05000272 ~ *""\ (.' (' r'I 95-2189 (10M) 12-89 R PDR ._,

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A.RAGE DAILY UNIT POWER LEV *

..

Docket No.: 50-272 Unit Name: Salem #1 Date: 06/10/92 Completed by: Mark Shedlock Telephone: 339-2122 Month May 1992 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 7 0 23 0 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 P. 8.1-7 Rl

'*

• OPERATING DATA REPORT

• Docket No: 50-272 Date: 06/10/92 Completed by: Mark Shedlock Telephone: 339-2122 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period May 1992

3. Licensed Thermal Power (MWt) 3411

4. Nameplate Rating (Gross MWe) 1170

5. Design Electrical Rating (Net MWe) 1115

6. Maximum Dependable Capacity(Gross MWe) 1149

7. Maximum Dependable Capacity (Net MWe) 1106

8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason NA

9. Power Level to Which Restricted, if any (Net MWe) N/A

10. Reasons for Restrictions, if any ~~~~~~~N~=A'--~~~~~~~~~~~

This Month Year to Date cumulative

11. Hours in Reporting Period 744 3647 130800

12. No. of Hrs. Rx. was Critical 0 2256.15 85856.43

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 0 2177.77 83165.71

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 7203120.0 262700265.2

17. Gross Elec. Energy Generated (MWH) 0 2416240 87220870

18. Net Elec. Energy Gen. (MWH) (2682) 2309203 83085776

19. Unit Service Factor 0 58.1 63.6 20~ Unit Availability Factor 0 58.1 63.6

21. Unit Capacity Factor (using MDC Net) 0 57.3 57.4 220 Unit Capacity Factor (using DER Net) 0 56~9 57.0

23. Unit Forced Outage Rate 0 6.1 21.0

24. Shutdowns scheduled over next 6 months (type, date and duration of each)

NA

25. If shutdown at end of Report Period, Estimated Date of Startup:

Jul 1992 8-l-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH MAY 1992 DOCKET NO.: -'5""0'-*-=-272:....:..____

UNIT NAME: Salem #1 DATE: 06/10/92 COMPLETED BY: Mark Shedlock TELEPHONE: 339*2122 METHOD OF SHUTTING LICENSE DURATION DOIJN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 0016 04/03/92 s 1391.33 c 1 ....... -......... -.... - RC FUELXX NUCLEAR NORMAL REFUELING

-*1

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1 2 3 4 5 F: Forced Reason Method: Exhibit G

• Instructions Exhibit 1

• Same S: Scheduled A-Equipment Failure (explain) 1-Manual for Preparation of Data Source B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3*Automatic Scram Event Report CLER) File

D-Requlatory Restriction 4-Continuation of (NUREG-0161)

E-Operator Training & License Examination Previous Outage F-Administrative S*Load Reduction G-Operational Error (Explain) 9*0ther H-Other (Explain)

MONTij: - MAY 1992

• SAFETY RELATED MAINTENANCE

• DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 JUNE 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 WO NO UNIT EQUIPMENT.* IDENTIFICATION 901106202 1 PASS PRESSURE MONITOR FAILURE DESCRIPTION: PASS PRESSURE MONITOR - FAILED INDICATION - REWORK 910514276 1 VALVE 1CV55 FAILURE DESCRIPTION: 1CV55 HAS A BODY TO BONNET LEAK -

REPLACE GASKET 920319190 1 CRDM LATCHING TOOL FAILURE DESCRIPTION: CRDM LATCHING TOOL AIR CYLINDER LEAKS - REPLACE 920512144 1 1B DIESEL GENERATOR FAILURE DESCRIPTION: REPLACE THE NO. 2L CYLINDER HEAD 920513171 1 12 CHARGING PUMP FAILURE DESCRIPTION: 12 CHARGING PUMP LUBE OIL COOLER LEAK - REPAIR 920523082 1 VALVE 12CS36 FAILURE DESCRIPTION: 12CS36 WILL NOT OPEN FROM THE CONTROL ROOM - INVESTIGATE

10CFR50.59 EVALUATIONS MONT~: - MAY 1992

• DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 JUNE 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. The station Operations Review Committee has reviewed and concurs with these evaluations.

ITEM

SUMMARY

A. Design Change Packages (DCP)

DCP# lEC-3165 Pkg. 1 "Reorientation of Turbine Front Standard Oil Gauges" - This modification repositions test gauges located in the turbine front standard housing to match the test valve positions. This will enhance operator interpretation and control of auto stop system test gauges and valves respectively during turbine automatic trip mechanisms operation testing. The existing gauge will be rearranged to match the order of the test valves. Additionally, a new pressure gauge will be added for the Autostop Oil System to monitor ASO Trip Testing. It will be installed in the portion of the AST Header which is isolated by the test lever. New highly readable nameplates will be installed. Test personnel shall be trained to perform the revised procedure with new and reoriented gauges. The proposed modification does not reduce the margin of safety as defined in the Technical Specifications because this modification will allow the operator to monitor the decay a repressurization of the Auto Stop Test Header.

This enhances the testing at the turbine from standard on a human factors basis. (SORC 92-055)

DCP# lEC-3161 Pkg. 1 "Installation of Reverse Power Relays on Unit 1 Generator" - This modification involves the installation of primary and backup reverse power relays interlocked with the existing Solid State Reactor Protection System Turbine Trip Contact K635 for generator protection against motoring above 6 megawatts of reverse power flow. The existing agastat timer which is interlocked with the existing K635 contact provides a 30 second time delay between the turbine trip and generator trip circuit. A time delay is required so that full reactor coolant flow can be maintained for at least 30 seconds during Condition II overpower transients to remove core heat and to prevent any reactor coolant pump overspeed conditions.

10CFR50.59 EVALUATIONS MONTH: - MAY 1992

• DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 JUNE 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (cont'd)

ITEM

SUMMARY

The existing agastat timer will be replaced with the 30 second timer of each reverse power relay.

This modification does not imapact the Technical Specification basis. (SORC 92-055)

DCP# lEC-3163 Pkg. 1 "Salem Unit 1 auto Stop Oil Trip" - The purpose of this change is to: 1.) Install pressure switches and relays to provide 2/3 logic for 20/ET actuation. 2.) Install 20-2/AST solenoid valves to ensure additional AST redundancy during hydraulic testing. 3.) Install keyed selector switches and relays to facilitate independent testing of each AST and OPC solenoid valve. This DCP does not reduce the margin of safety as defined in the basis for any Technical Specification. No changes to Technical Specification setpoints, flow, or equipment ratings have been made. (SORC 92-056)

DCP# lEC-3099 Pkg. 1 "Replacement of Rosemount Electronic Pressure and Differential Pressure Transmitters" - The purpose of this change is to: 1.) Replace 55 Rosemount electronic pressure and differential pressure transmitters with equivalent series H transmitters. 2.) Upgrade 16 Rosemount electronic quick~ disconnect at the transmitters. 3.)

Install new electrical quick-disconnect at the transmitters. 4.) Modify the tubing at the transmitters for proper arrangement of valving.

There is no change to instrument process variable spans. The new or modified transmitters are equal to or better than the previous instruments under all conditions. There is no impact on the margin of safety as defined in the basis for any Technical Specification. (SORC 92-057)

DCP# lSC-2267 Pkg. 2 "SEC Containment Spray Actuation" - This change package will modify the existing Safeguards Equipment Control Cabinets (SEC) for the A and c Vital Buses. *This will prevent the possibility of the simultaneous starting of containment spray pumps and service water pumps on the Emergency Diesel Generator during an accident plus a loss of offsite power (Mode III) or associated bus undervoltage (Mode IV) coincident with Containment

10CFR50.59 EVALUATIONS MONTH: - MAY 1992

• DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 JUNE 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (cont'd)

ITEM

SUMMARY

High-High Pressure. Additional contacts are being added to eliminate the possibility of simultaneous loading of pumps to the diesel. As per evaluation S-C-CBV-NSE-0797, containment pressure and temperature do not exceed design limits. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 92-057)

DCP# lEC-3134 Pkg. 1 "Salem Security Upgrade" - This change package enhances the security boundary intrusion detection at the Salem Service Water Intake Structure (SWIS) and the Salem Circulating Water Intake Structure (CWIS). Three intrusion detection systems are being added to both the SWIS and the CWIS. These system are: 1.) Vertical infrared system on the inside of the parallel to the protected boundary fence at the trash rakes. 2.) Horizontal infrared system detecting intrusion up thru the removable grates above the bar rakes. 3.) Fiber optic Aquamesh systems detecting intrusion from the river into the trash basket pits via the trash basket water outfall. The outputs from these systems are being attached to existing security zones in the area of the devices. Intrusion in any of these areas will alarm in the Central Alarm Station the Secondary Alarm Station. It was determined that the Technical Specifications neither directly or indirectly address the plant security system. Therefore, this DCP does not reduce the margin of safety as defined in the Technical Specifications. (SORC 92-059)

DCP# lEC-3085 Pkg. 1 "Control Room Modifications" - This DCP was issued to implement the corrective actions required to resolve sixteen of the Human Engineering Discrepancies (HED) identified in the Salem Unit 1 Control Room. The HEDs were generated during the Detailed Control Room Design Review conducted in accordance with NRC NUREG-0700 requirements. a review of the Technical Specifications did not identify any setpoint, operational limit or design limit which is impacted by these modifications.

There is no reduction to the margin of safety as defined in the basis for any Technical Specifications. (SORC 92-063)

10CFR50.59 EVALUATIONS MONTH: - MAY 1992

• DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 JUNE 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (cont'd)

ITEM

SUMMARY

DCP# 1EC-3171 Pkg. 1 "Installation of Stainless steel Ladder in Lower Reactor Refueling Cavity" - The purpose of this change is to install a removable stainless steel ladder in the lower reactor cavity, el. 104 1 -1 1 4 11 to 94 1 -0 11 in Salem Unit #1. Since the addition of a ladder does not compromise the structural integrity of the reactor cavity liner there is no reduction in the margin of safety as defined in the basis of any Technical Specification.

(SORC 92-062)

B. Procedures and Revisions VS1.RE-FR.ZZ-0004(Q) "Cycle X-XI Refueling" - The purpose of this revision is to change steps in the Insert Changeouts and Core Reload sections of the Cycle X-XI Refueling Procedure to accommodate the revised core loading plan. [NOTE: The cor.e loading plan was revised due to damaged fuel discovered during the 1R10 UT/VT fuel inspection.] Revised the SFP maps and reactor core map as needed to reflect the above changes.

The proposed change will not reduce the margin of safety as defined in the basis for the Technical Specifications since no T/S Limiting Conditions for Operation will be violated. The charging system and boron injection flowpaths will be maintained in accordance with the Technical Specifications. (SORC 92-059)

c. Temporary Modifications TMR# 92-004 "Installation of Temporary Jumper Cables" - The purpose of this TMOD is to provide for installation of class 1E temporary jumper cables as required. These modifications are required to supply temporary power to the #11 fuel Handling Building Exhaust Fan, Radiation Monitor R41A, B &

c Pump and 1RP4 Status Panel. These jumper cables are fastened by means of tie-wraps to the existing conduit, cable trays and cable tray support members located in the proximity. The above mentioned cables supports have been evaluated and found to be adequate to support the cables during a design basis earthquake event. There is no reduction in the margin of safety as defined in the Technical Specifications. (SORC 92-059)

.*

10CFR50.59 EVALUATIONS MONTH: - MAY 1992

• DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 JUNE 10, 1992 COMPLETED BY: J. FEST

'l'ELEPHONE: (609)339-2904 (cont'd)

ITEM

SUMMARY

D. Deficiency Reports (DR) - "Use-As-Is" DR SMD 92-262 "Primary Water Storage Tank" - This evaluation addresses the normal use of the Primary Water Storage Tank (PWST) as a source of water for Reactor makeup, resin sluicing, etc., with the rubber diaphragm having sunk to a location on or near the bottom of the tank. The Unit 1 Primary Water Storage Tank's diaphragm cannot be kept afloat as originally designed. It appears the sinking is due to diaphragm breach. However, the exact location of the breach is unknown. The Primary Water Makeup Pump suction line has an in-line suction strainer to block any debris from entering the pumps. In the event that a piece of diaphragm material should enter the suction piping, it would be prevented from further travel by the suction strainer. The inadvertent blocking of the Primary water flow does not jeopardize or impact any equipment necessary for ensuring the bases for the Technical Specification concerning boration or reactivity control. The associated margin of safety is not reduced. (SORC 92-057)

E. Safety Evaluations S/E NFU 92-308 "Salem Unit 1 Cycle 11 Core Loading Pattern and Safety Evaluation for Operation in All Modes and NRC Notification" - This safety evaluation takes credit for Cycle 11 specific core physics data.

In addition, this safety evaluation takes credit for a Containment High High setpoint reduction to 15.0 psig. Attachment lB provides the Westinghouse safety evaluation for Salem Unit Cycle 11 operation in all modes with excessive AFW flow and delay in Containment Spray initiation time. The safety evaluation shows that the analysis acceptance criteria continue to be met.

Thus the margin of safety as defined in the Technical Specifications is not reduced.

(SORC 92-062)

S/E HHB SGS U1&2 "Contamination of #1 HHB" - This Safety Evaluation (SE) provides justification IAW requirements established in IE Bulletin 80-10 Action step 2 for

10CFR50.59 EVALUATIONS MONTH: - "MAY 1992

'

• DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 JUNE 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (cont'd)

ITEM

SUMMARY

the continued operation of the normally non-radioactive House Heating Boiler (HHB) system. On April 30, 1992, the number 1 HHB was found to be contaminated with low levels of .cs-134 and Cs-137 at approximately 4;8E-07 Ci/ml. IE 80-10 states that "If these nonradioactive systems are or become contaminated, further use of the system .shall be restricted until the cause of the contamination is identified and corrected and the system has been decontaminated. Decontamination should be performed as soon as possible. However, if it is considered necessary to continue operation of the system as contaminated, an immediate safety evaluation of the operation of the system as a radioactive system must be performed IAW the requirements of 10CFR50.59."

The margin of safety as defined in the Technical

• Specifications is not reduced. Routine samples of the HHB are obtained monthly IAW IE 80-10. If contamination occurs, increased sampling frequencies shall be performed to ensure compliance with the Te~hnical Specification requirements. (SORC 92-060)

SCN 92-21 "Salem SAR Change Notice 92-21 11 - The proposed change revises UFSAR Sections 6.1.1.4, 6.2.2.2.2, 9.2, 9.4.2.1, 9.4.4.3.1, 15.4.8.1.2, UFSAR Tables 6.3-13 and 15.4-22 to reflect the Salem Units 1&2 service water supply design temperature change from s5°F to 90°F. This modification is to the design temperature only and does not alter the function or operation of any system or component.

There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 92-063)

SCN 92-07 "Salem SAR Change Notice 92-07 11 - The purpose of this revision is to provide conclusions that the changes to the operation of the Main Steam System Chemical Feed System (Chemical Feed System),

specifically the ammonium hydroxide system, as well as the receipt of bulk tanker procedures will enable.the Salem Generating Station (SGS) control room to remain habitable during a postulated accidental release of ammonium hydroxide.

10CFR50.59 EVALUATIONS MONTH: - *MAY 1992

• DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 JUNE 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (cont'd)

ITEM

SUMMARY

The implemented changes will assist in keeping the control rooms habitable following a postulated accidental release of ammonium hydroxide, therefore the margin of safety, as defined in the basis of the Technical Specifications is not reduced. {SORC 92-062)

TEMP-LCO-RMCOOLERS "Temporary Addendum to Effects of Inoperable Room Coolers" - The purpose of this proposal is to use Calculation S-l-ABV-MDC-1098, Rev. o and Engineering Evaluation S-1-ABV-MEE-0725, Rev. o to demonstrate the operability of RHR pump 12, without service water being available to its associated room cooler, for loading fuel into the Unit 1 core starting May, 1992. This proposal neither changes the configuration of the plant as described in Section 6.0 and 9.0 of the UFSAR nor adds any new equipment. This proposal also does not alter the design performance requirements of the safety related equipment described in Sections

• 6.0, 9.0 and 15 of the UFSAR. This proposal raises the UFSAR value of RHR pump 12 ambient room temperature from 110°F to 120°F, but demonstrates that the equipment in RHR pump 12 room is qualified to operate at 120°F. This proposal also allows the operation of RHR pump 12 without its room cooler, provided the room temperature does not exceed 120°F. There is no reduction in the margin of safety as defined the basis of the Technical Specifications.

{SORC 92-062)

IR 92-320 "Hope Creek Generating Station Fire Water System"

- The purpose of this 10CFR50.59 Review and Safety Evaluation is to assess the adequacy of the Hope Creek Generating Station {HCGS) fire water system as backup fire suppression system for Salem Generating Station {SGS) Units 1 and 2 without introducing a potential Unreviewed Safety Question for either SGS or HCGS. The role of the fire suppression water system is to support fire suppression and does not contribute to the probability of a fire. Therefore, the source of the fire suppression system does non increase the probability of an accident previously evaluated in the SAR. Since the fire suppression water system

10CFR50.59 EVALUATIONS MONTH: - 'MAY 1992

• DOCKET NO:

UNIT NAME:

DATE:

50-272 SALEM 1 JUNE 10, 1992 COMPLETED BY: J. FEST TELEPHONE: (609)339-2904 (cont'd)

ITEM

SUMMARY

at HCGS is capable of providing the pressure and flow required at SGS, and the NRC guidelines do not require that unrelated simultaneous fires be assumed, the consequences of an accident (in this case a fire) previously evaluated in the SAR are not increased. Therefore, given a single fire, the margin of safety required by the Technical Specifications is not reduced. {SORC 92-062)

• SALEM GENERATING STATION

• MONTHLY OPERATING

SUMMARY

- UNIT 1 MAY 1992 SALEM UNIT NO. 1 The Unit was shutdown for the entire period for the 10th Refueling outage.

,_

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.J

• REFUELING INFORMATION MONTH: - *MAY 1992

• DOCKET NO:

UNIT NAME:

DATE.:

50-272 SALEM 1 JUNE 10, 1992 COMPLETED BY: J. FEST T.ELEPHONE: (609)339-2904 MONTH MAY 1992

1. Refueling information has changed from last month:

YES X NO

2. Scheduled date for next refueling: APRIL 4, 1992

3. Scheduled date for restart following refueling: JUNE 26, 1992

4. a) Will Technical Specification changes or other license amendments be required?:

YES NO NOT DETERMINED TO DATE x b) Has the reload fuel design been reviewed by the Station Operating Review Committee?:

YES x NO If no, whert is it scheduled?:

5. Scheduled date(s) for submitting proposed licensing action:

N/A

6. Important licensing considerations associated with refueling:

7. Number of Fuel Assemblies:

a. Incore 193

b. In Spent Fuel Storage 656

8. Present licensed spent fuel storage capacity: 1170 Future spent fuel storage capacity: 1170

9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: September 2001 8-l-7.R4