ML18101A227
| ML18101A227 | |
| 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 9409220218 | |
| Download: ML18101A227 (11) | |
Text
'CPS~G*
Public Se'rvice l;lectric 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. 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 August 1994 are being sent to you.
Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions 10CFR50.59 Evaluations Operating Summary Refueling Information Sincerely yours, ager -
at ions RH:pc cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 The EnermLPeonJe
,- _____ _. - - - - - - - - \ j&~**'I
- 8-1!..7. R2 *
- AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-272 Unit Name: Salem #1 Date: 09/09/94 Completed by: Mike Morroni Telephone: 339-5142 Month August 1994 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1064 17 1135 2 1065 18 1085 3 1054 19 1079 4 1072 20 1071 5 1063 21 1012 6 1064 22 807 7 1075 23 825 8 1074 24 333 9 1051 25 0 10 1110 26 0 11 1103 27 0 12 1053 28 0 13 1079 29 0 14 1053 30 0 15 1095 31 0 16 1083 P. 8.1-7 Rl
- OPERATING DATA REPORT Docket No: 50-272 Date: 09/09/94 Completed by: Mike Morroni Telephone: 339-5142 Operating Status
- 1. Unit Name Salem No. 1 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 ~~~~----=N~A=-~~~~~~~~~~~~~
This Month Year to Date Cumulative
- 12. Hours in Reporting Period 744 5831 150528
- 12. No. of Hrs. Rx. was Critical 744 3658.6 98790.6
- 13. Reactor Reserve Shutdown Hrs. 0 0 0
- 14. Hours Generator On-Line 564.2 2939.3 94827.2
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (MWH) 1861456.8 9811142.4 300583456.4
- 17. Gross Elec. Energy Generated (MWH) 613950 2890280 99426250
- 18. Net Elec. Energy Gen. (MWH) 582339 2690410 94627963
- 19. Unit Service Factor 75.8 50.4 63.0
- 20. Unit Availability Factor 75.8 50.4 63.0
- 21. Unit Capacity Factor (using MDC Net) 70.8 41.7 56.8
- 22. Unit Capacity Factor (using DER Net) 70.2 41.4 56.4
- 23. Unit Forced Outage Rate 24.2 41.1 21.8
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
None.
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
N A.
UNIT SHUTDOYN AND POYER REDUCTIONS REPORT MONTH AUGUST 1994 DOCKET NO. :-'5""0"'"*=27""2'"""'"_ __
UNIT NAME: Salem #1 DATE: 09-09-.94 COMPLETED BY: Mike Morroni TELEPHONE: 339-5142 METHOD OF SHUTTING LICENSE DURATION DOYN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTiON -
NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 1671 08-21-94 F 39.2 A 5 ---------- HH PUMP XX CONDENSATE PUMP 1678 08-23-94 F 29.4 A 5 ---*------ HH PIPEXX CONDENSATE PIPING 1682 08-24-94 F 179.8 A 5 ---------- HH PIPEXX CONDENSATE PIPING 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 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain)
10CFR50.59 EVALUATIONS MONTH: - AUGUST 1994
~
e DOCKET NO:
UNIT NAME:
DATE:
50-272 SALEM 1 SEPTEMBER 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (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 lEC-3264 Pkgs 1 & 2 "lA & lB 460V Vital Bus Transformer Replacement" -
These DCPs replace the lA & 1B-480V Vital Bus 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 modifi6ations 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) lEC-3206 Pkg 1 "Analog Feedwater Control System Replacement" -
The purpose of this DCP is to convert the existing Salem Unit 1 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
10CFR50.59 EVALUATIONS MONTH: - AUGUST 1~94 e
DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
50-272 SALEM 1 SEPTEMBER 10, 1994 R. HELLER TELEPHONE: (609)339-5162 (cont'd)'
ITEM
SUMMARY
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) lEC-3238 Pkg 1 "SW Pipe to SGFP - TLOC" - The carbon steel portions of the service water system are being replaced with a corrosion resistent material as the primary objective of the service water upgrade project. This installation in the area immediate to the Steam Generator Feedpump Turbine Lube Oil Coolers. The new piping is detailed on dwg.
224642-A-1236, MD-003. This proposal does not reduce the margin of safety as defined in the basis for any Technical Specification. The Technical Specification has no applicability to Service Water in the Turbine Building.
(SORC 94-064) lEC-3292 Pkgs 1&2 11 11 CCHX Control System Upgrade" - This Design Change Package removes the existing CCHX flow controller 1FA3891C and temperature controller 1TA9286C for valves 11SW122 and 11SW127 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 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)
I i
10CFR50.59 EVALUATIONS e e DOCKET NO: 50-272 MONTH: - AUGUST 1994 UNIT NAME: SALEM 1 DATE: SEPTEMBER 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)'
ITEM *
SUMMARY
lEC-3347 Pkg 1 "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) lEC-3311 Pkg 1 "Auxiliary Building Ventilation System Modification (HV--0006)" - This project provides design enhancements and refurbishments which will improve the ABV system performance and reliability and reduce auxiliary building pressure problems.
The enhancements simplify the way the system operates which will facilitate balancing and also reduce maintenance requirements. The revised system will continue to modulate air flow in response to building pressure; however, the supply fan inlet guide vane dampers which currently modulate based on temperature, will be revised to provide two position operation. In addition, the different air flow requirements to the ECCS pump cubicles between normal and emergency system operation will be eliminated to allow for stabilization of building pressures. The exhaust fans pressure control instrumentation hardware will be replaced by equivalent qualified ones.
The operation of the supply fans inlet guide vane controls, the pump room damper operators, and the building differential pressure switch controls do not impact or perform a safety function discussed in the any Technical Specifications or their bases. Therefore, this proposal does not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 94-065)
10CFR50.59 EVALUATIONS MONTH: - AUGUST 1994 DOCKET NO:
UNIT NAME:
DATE:
50-272 SALEM 1 SEPTEMBER 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)
ITEM
SUMMARY
lEC-3313 Pkg 1 "Pressurizer Upgrade" - This DCP provides upgrades for components located in the pressurizer enclosure to improve operability , maintainability and component service life. The modifications include: 1.) replacing the pressurizer spray bypass valves 1PS2 and 1PS4 with new valves and removing their associated remote valve operators, 2.) replacing selected environmentally qualified (EQ) cables in the pressurizer enclosure that have been experiencing premature degradation due to high temperature exposure with cables that have a higher temperature rating, and 3.) routing of control air tubing for pressurizer spray valves lPSl and 1PS3 positioners and E/P transducers.
The pressurizer spray bypass valves, the pressurizer spray valves and the E/P transducers are not discussed in any of the Technical Specifications or their design bases. Therefore, this modification will not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 94-065) lEE-0083 Pkg 1 "Equivalent Replacement of 11 Condensate Pump Discharge Stop Bypass Valve 11CN106" - The 11CN106 is being replaced due to damage to the valve internals which caused the valve to leak by. This modification will replace the existing 2 11 600#
Class, Hancock globe valve, with a new 2 11 800#
Class, Hancock globe valve. The selected valve is dimensionally the same, is the same material grade, and has the same valve coefficient as the valve being replaced. The proposed modification is an equivalent replacement of a non-safety related, Seismic 3 component located in a non-vital area of the plant. The component is not required for safe shutdown of the plant. This modification will not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 94-066)
10CFR50.59 EVALUATIONS MONTH: - AUGUST 1994 DOCKET NO:
UNIT NAME:
50-272 SALEM 1 DATE: SEPTEMBER 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)'
ITEM
SUMMARY
lEC-3332 Pkg 1 "Replacement of Degraded Pipe and Fittings" - This DCP replaces selected carbon steel fittings and pipe segments with chrome alloy and carbon steel materials, and in some cases, heavier wall materials. Fittings and replacements will be processed as emergent items as they develop. In cases where upgraded material is not available within the schedule constraints, replacement with carbon steel will be implemented. The replacement of worn fittings and pipe segments will restore the plant to its analyzed configuration. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 94-068)
- c. Temporary Modifications (T-Mods)
T-Mod 94-081 "Unit 1 - Clear INPO Finding on High Oxygen in PWST" - This T-Mod places a mechanical jumper between the Restricted DM Water System (DR) from upstream of 1DR4 to the #11 Primary Water Makeup Pump (1WRE9) pump discharge piping flange. The 90 degree elbow upstream from 1DR4 will be replaced by a temporary tee. A reducer will be attached to the open branch of the tee. A shutoff valve (1DR172) will be installed on the other side of the reducer. The pump casing for #11 Primary Water Makeup Pump (1WRE9) will be removed. A temporary 90 degree elbow will be connected by temporary piping which meets the DR piping code SPS20C. The Technical Specifications do not address the Primary Water Makeup System.
Therefore, there is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-064)
SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT 1 AUGUST 1994 SALEM UNIT NO. 1 The Unit began the period operating at full power and continued to operate at essentially 100% power until August 22, 1994, when power was reduced to 75% to perform maintenance on #13 condensate pump. A pressure transient in the condensate system was experienced on August 24, 1994, and appears to have damaged pipe hangers. The Unit was removed from service to investigate and repair the damage. The repairs were completed and the Unit was synchronized on August 31, 1994. The Unit was in a power escalation, as the period ended.
I REFUELING INFORMATION MONTH: - AUGUST 1994 *
- DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
50-272 SALEM 1 SEPTEMBER 10, 1994 R. HELLER TELEPHONE: (609)339-5162 MONTH AUGUST 1994
- 1. Refueling information has changed from last month:
YES NO X
- 2. Scheduled date for next refueling: APRIL 8, 1995
- 3. Scheduled date for restart following refueling: JUNE 6, 1995
- 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?: MARCH 1995
- 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 732
- 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