ML18101A226

Monthly Operating Rept for Aug 1994 for Salem Unit 2. W/940914 Ltr

ML18101A226
Person / Time
Site:	Salem
Issue date:	08/31/1994
From:	Morroni M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9409220193
Download: ML18101A226 (12)

Text

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• S'!'!l'vice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station September 14, 1994 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 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 August 1994 are being sent to you. RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions 10CFR50.59 Evaluations Operating Summary Refueling Information Sincerely yours, ager -tions cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 9409220193 940831 PDR ADOCK 05000311 R PDR 95-2189 (10M) 12-89

• AVERAGE DAILY UNIT POWER LEVEL / _., ,. z..*-Completed by: Mike Morroni Month August 1994 Day Average Daily Power Level (MWe-NET) 1 1010 2 1076 3 1029 4 1039 5 830 6 1063 7 985 8 1068 9 1050 10 1027 11 662 12 768 13 1016 14 1021 15 1028 16 1052 P. 8.1-7 Rl Docket No.: 50-311 Unit Name: Salem #2 Date: 09-09-94 Telephone:

339-5142 Day Average Daily Power Level (MWe-NET}

17 993 18 976 19 1019 20 1033 21 1020 22 984 23 1026 24 1028 25 1030 26 1023 27 1'060 28 1017 29 1080 30 1067 31 753

• OPERATING DATA REPORT

• Docket No: 50-311 Date: 09/09/94 Completed by: Mike Morroni Telephone:

339-5142 Operating Status 1. Unit Name Salem No. 2 Notes 2. Reporting Period August 1994 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

11. Hours in Reporting Period 12. No. of Hrs. Rx. was Critical 13. Reactor Reserve Shutdown Hrs. 14. Hours Generator On-Line 15. Unit Reserve Shutdown Hours 16. Gross Thermal Energy Generated (MWH) Gross Elec. Energy Generated (MWH) 18. Net Elec. Energy Gen. (MWH) 19. Unit Service Factor 20. Unit Availability Factor 21. Unit Capacity Factor (using MDC Net) 22. Unit Capacity Factor (using DER Net) 23. Unit Forced Outage Rate This Month 744 744 0 744 0 2452857.6 773360 739975 100 100 89.9 89.2 0 Year to Date cumulative 5831 112944 5467.8 74747.3 0 0 5261.1 72150.6 0 0 15951585.6 178414525.0 5106240 75652758 4856438 71983715 90.2 63.9 90.2 63.9 75.3 57.6 74.7 57.2 8.2 21. 8 24. Shutdowns scheduled over next 6 months (type, date and duration of each) Refueling outage scheduled to start October 15, 1994. Duration is to be determined.

25. If shutdown at end of Report Period, Estimated Date of Startup: NA 8-1-7.R2 NO. DATE 1622 08-11-94 F 1623 08-11-94 F 1673 08-22-94 F 1706 08-31-94 F 1 2 F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH AUGUST 1994 DURATION TYPE 1 (HOURS) REASON 2 .3 A 4.1 A 2.5 A 17.5 A Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction METHOD OF SHUTTING DOWN REACTOR 5 5 5 5 E-Operator Training & License Examination F-Administrative

• G-Operational Error (Explain)

H-Other (Explain)

LICENSE EVENT SYSTEM REPORT # CODE 4 ----------

HA ----------

HF ----------

WG ----------

HF 3 Method: 1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther COMPONENT CODE 5 DOCKET NO. UNIT NAME DATE COMPLETED BY TELEPHONE 50-311 Salem #2 09-09-94 Mike Morroni 339-5142 *, ,_ I CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE GENERA EXCITER FIELD RHEOSTAT PUMP XX CIRCULATING WATER PUMPS PUMPXX OTHER CLOSED COOLING WATER SYST. PROBLEMS HTEXCH CONDENSER TUBE AND WATERBOX CLEAN 4 5 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Exhibit 1 -Same Source Event Report CLER) File (NUREG-0161)

°10CFR50.59 EVALUATIONS MONTH: -AUGUST 1994

• DOCKET I: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-311 SALEM 2 SEPTEMBER 10, 1994 R. HELLER (609)339-5162 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 (DCPs) 2EC-3249 Pkg 1 2EC-3286 Pkg 1 2EC-3230 Pkg 1 "Cable Protection DCP" -This modification provides improved cable protection of the subject circuits without limiting the load capability and also improves the protection and operability of the equipment.

One recommendation of the evaluation which will be implemented in this DCP, is to remove the jumpers from the heater overload circuits that are presently in place on safety related MOVs. The overload relay heaters will be sized in accordance with Calculation ES-18.006.

This DCP resolves inadequacies identified in evaluation S-C-ZZ-EEE-0873, by implementing the recommended solutions for the protection of various #12 and #14 AWG safety related cables for Salem Generating Station Unit 2. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-062) "Diesel Generator Combustion Air Modification" -The modifications involve (1) truncating the exhaust piping on the Auxiliary Building roof and enclosing the remaining pipe in a protection shell of larger pipe and concrete wall, for protection from tornado wind loads and missiles, (2) installing a tornado missile proof barrier at the diesel generator air intake opening in the Auxiliary Building wall, (3) installing a pipe support, attached to the Auxiliary Building ceiling, for the exhaust pipe and for the intake pipe to limit pipe movement during an quake and (4) installation of a spring hanger attached to the Auxiliary Building ceiling for the exhaust pipe. Analyses of the tornado loads. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-062) "Circulating Water Trash Rake Upgrade" -This modification will: Install a new traversing trash rack rake on the existing rails of the Circulating

,a '10CFR50.

59 EVALUATIONS MONTH: -AUGUST 1994

• DOCKET I UNIT NAME: 50-311 SALEM 2 ./ (cont'd) ITEM DATE: COMPLETED BY: TELEPHONE:

SUMMARY

SEPTEMBER 10, 1994 R. HELLER (609)339-5162' Water Intake Structure (CWIS). The new rake has improved rack cleaning ability by the use of a clamshell type gripper head. Install a third rail on the deck of the CWIS as a mechanical restraint to prevent the rake from tripping should the load limiters fail. Provide power for the new rake from the existing Unit 2 source. Install a new Unit 2 power source for the existing trash rake. Power connections will be quick disconnect type. Either rake can traverse the intake structure and clean the trash rake on either unit. Install a raised cable tray on the CWIS exterior wall to contain retractable power cables from both rakes. The proposed modifications do not reduce the margin of safety as defined in the basis for any Technical Specification because the CW system and trash rake are not addressed in the Salem Technical Specifications. (SORC 94-062) 2EC-3272 Pkgs 1-3 11 2A, 2B, 2C 460V and 230V Transformer Ammeter Installation" -The permanent of an individual ammeter for each of the 2A, 2B and 2C 460V and 230V transformers, thus allowing routine monitoring of the transformer loads by the station operators.

These ammeters would be located at the 2B4D 4KV switchgear cubicle on El. 64 of Unit 2. Monitoring of the current supported by each of the transformers listed above requires the services of electricians, at present, to take manual measurements (in the absence of permanently installed ammeters)

• It is important to monitor the loading of these safety-related transformers, as was brought out in the 1993 NRC EDSFI (Item Nos. H39 and H40). Reference EWR NO. 62-93-9169.

The addition of the 460V and 230V ammeters has no control function and will be utilized by the operators during routine surveillance procedures to monitor vital transformer loading. Therefore, the indication benefit of the ammeters has no affect on any operability/safety margins utilized in plant operations. (SORC 94-062) 2EC-3219 Pkgs 1&2 11 2A & 2B 460V Vital Bus Transformer Replacement" -These DCPs replace the 2A & 2B-480V Vital Bus lOCFR50.59 EVALUATIONS MONTH: -AUGUST 1994 (cont'd) ITEM 2EC-3178 Pkg 1 2EC-3229 Pkg 1

• DOCKET I UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-311 SALEM 2 SEPTEMBER 10, 1994 R. HELLER (609)339-5162 transformers with ones of the same type, but with increased capacity, and the replacement transformers will have additional insulation between the middle layers of the high voltage coils. The original transformers*were rated 750/1000 KVA at 150 degrees c temperature rise, and the replacements will be rated 1000/1333 KVA at 80 degrees C temperature rise. There are no changes in the types of insulation or its temperature ratings. The six ventilating fans furnished with the transformers will be essentially the same as the originals.

The temperature control relays will be reset to start the fans at 120 degrees c, and the alarm set points at 130 degrees c and 140 degrees c consistent with the 80 degrees C temperature rise ratings of the transformers.

These modifications actually increase the margin of safety since the replacement transformers have greater capacity, lower temperature rise, and more insulation to protect against internal transformer failure. (SORC 94-062) "Analog Feedwater Control System Replacement" -The purpose of this DCP is to convert the existing Salem Unit 2 analog feedwater control system to a microprocessor based digital feedwater control system. Specifically, provide automatic control of steam generator water level over the range of power operation, add signal validation algorithms for input signals, eliminate the steam/feedwater flow mismatch coincident with low steam generator water level reactor trip function, incorporate the atmospheric relief valves (MSlOs) in to the digital feedwater control system. A review of the Technical Specifications did not identify any safety limits, limiting safety system settings, setpoint, operational limit or design limit whose margin of safety are impacted by this modification.

{SORC 94-063) "Small Bore Piping Replacement" -This DCP primarily entails the replacement of safety related and non-safety related small bore piping (2 inch and smaller) for portions of various plant systems. In addition, a small quantity of non-safety related lOCFR50.59 EVALUATIONS MONTH: -AUGUST 1994 i ) {cont'd} ITEM 2EC-3252 Pkgs 1&2

• DOCKET I: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-311 SALEM 2 SEPTEMBER 10, 1994 R. HELLER (609)339-5162 large bore piping will also be replaced.

In general, the existing piping is schedule 40, A-106 carbon steel, which is being replaced with schedule 80 A-335, P22 chrome-moly.

In certain areas, alternate piping materials such as 316 stainless steel will be installed for severe erosion/corrosion conditions.

Replacement piping will follow the original routing wherever possible, and the existing pipe supports will also be re-used wherever possible.

Piping design and pipe supports will only be modified where necessary.

Existing carbon steel globe valves and gate valves in the affected lines will be replaced with new globe valves of improved design, having chrome-moly bodies. Existing insulation on the affected lines will be demolished and scrapped.

Replacement piping will be reinsulated using new calcium silicate material with stainless steel lagging. During the review of the Technical Specifications, it was found that no details for either the small bore piping and components or the three inch f eedwater heater piping are addressed.

Therefore, there is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-063} 11 21 CCHX Control System Upgrade" -This Design Change Package removes the existing CCHX .flow controller 2FA3891C and temperature controller 2TA9286C for valves 21SW122 and 21SW127 respectively, and replaces them with a single pneumatic cascade type control system. The cascade control system will utilize both temperature and flow as input and will modulate each valve simultaneously by providing a single control air signal to the valve positioners.

This will result in a more even distribution of pressure drop, and will reduce the potential for damage caused by cavitation.

The new cascade control system as well as the interim installation and test conditions associated with this modification will not impact the ability of the Service Water or Component Cooling Water systems to perform their intended safety functions, and will be in full compliance lOCFR50.59 EVALUATIONS MONTH: -AUGUST 1994 (cont'd) ITEM 2EC-3299 Pkg 1 2EC-3307 Pkg 1 2EE-0059 Pkg 1

• DOCKET I: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-311 SALEM 2 SEPTEMBER 10, 1994 R. HELLER (609)339-5162 with the Technical Specifications.

Therefore, this DCP does not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 94-064) "Rod Control Timing Change" -The purpose of this DCP is to change the rod control timing such that no single failure can result in asymmetric rod withdrawal.

This is a PSE&G commitment to the NRC in PSE&G's response to Generic Letter 93-04, as detailed in NLR-N93152.

This DCP also incorporates rod control surveillances as recommended by the Westinghouse Owner's Group. The proposed timing changes do not affect the margin of safety as defined in the basis for any Technical Specification.

A generic safety evaluation has been performed by WOG which concluded that all safety limits continue to be met. The timing change in combination with the rod control surveillance tests increase the reliability of the rod control system. (SORC 94-065) "Polar Crane Trolley Understructure Strengthening and Load Derating" -A steel plate stiffener and two gusset plates shall be added underneath the plate deck of the polar crane trolley. The addition of the member near the external reduction gear bearing and limiting the crane capacity will enable the crane to be used without overstressing the sheave nest bolts and the trolley understructure.

No Technical Specifications were found referencing the polar crane, its support structure, or its capacity.

This proposal does not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 94-065) "No. 24 Service Water Pump Discharge Check Valve (24SW2) Replacement" -The proposed modification entails the replacement of No. 24 Service Water Pump Discharge Check Valve 24SW2. The existing valve is a C&S Valve Co. Dual Plate, soft seat, aluminum bronze valve, which has a history of erosion problems due to the soft seat becoming separated

' '

• EVALUATIONS MONTH: -.AUGUST 1994 / / -. _,_...., (cont'd) ITEM 2EC-3271 Pkg 1

• DOCKET I UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-311 SALEM 2 SEPTEMBER 10, 1994 R. HELLER (609)339-5162 from the valve body and allowing the valve to leak by. The replacement valve is a C&S Valve Co. Dual Plate, hard seat, 6% molybqenum stainless steel valve, which has excellent erosion/corrosion characteristics, and is the selected equivalent valve of choice. The seat material for the new valve is the same as the valve body and should exhibit the same excellent erosion/corrosion resistance.

The replacement valve is dimensionally the same, no piping modifications are required.

The form, fit and function of the replacement valve remain the same. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-067) "2F 230V Transformer Replacement" -This modification replaces the 2F 230V non-vital transformer with a transformer having the same cagacity of 750KVA and a future rating of lOOOKVA at 80 c temperature rise. The replacement transformer will have an added layer of insulation between the middle layers of the high voltage winding of each coil, which is an area where failures have occurred on some of the original transformers.

These modifications actually increase the margin of safety since the replacement transformer has greater capacity, lower temperature rise, and more insulation to protect against internal transformer failure. (SORC 94-068) B. Temporary Modifications (T-Mods) T-Mod 93-140 "Upgrade Hoisting Capacity of the Fuel Handling Crane From 5 Tons to 20 Tons" -The purpose of this modification is to increase the capacity of the spent fuel pool. The existing nine Exxon racks will be removed and replaced with nine new Holtec racks. Also, three Exxon racks will be relocated in the SFP. This T-Mod will install a new trolley and hoist for the removal and installation of racks. The existing trolley and hoist will be used for removing the spent fuel. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-068)

SALEM UNIT NO. 2 *

• SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT 2 AUGUST 1994 The Unit began the period shutdown as investigations into the June 29, 1994 reactor trip continued.

On July 3, 1994, the Unit was cooled down to Mode 5, "Cold Shutdown," due a flange leak on 22 Reactor Coolant Pump. The repairs were completed and startup activities commenced.

On July 13, 1994, during the power escalation, power was briefly held at 90% for resolution of a heater drain pump control valve problem. Power was increased to 100% on July 14, 1994, and the Unit continued to operate at essentially full power throughout the remainder of the period.

I *, ._ RaFbELING INFORMATION MONTH: -. AUGUST 1994 ' ' ,I MONTH AUGUST 1994

• DOCKET I: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

1. Refueling information has changed from last month: YES X

• NO ___ _ 2. Scheduled date for next refueling:

OCTOBER 15, 1994 50-311 SALEM 2 SEPTEMBER 10, 1994 R. HELLER (609)339-5162

3. Scheduled date for restart following refueling:

DECEMBER 13, 1994 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 NO __ X=-=---If no, when is it scheduled?:

OCTOBER 94 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 556 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:

March 2003 8-l-7.R4