ML20115F975

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Monthly Operating Rept for Mar 1985
ML20115F975
Person / Time
Site: Salem PSEG icon.png
Issue date: 03/31/1985
From: Ronafalvy J, Zupko J
Public Service Enterprise Group
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8504220079
Download: ML20115F975 (26)
v • d • e


Text

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l AVERAGE D1ILY NIT POWER LEVEL Docket No. 50-311 Unit Name Salem # 2 Date. April 10,1985 Completed by J. P. Ronafalvy Telephone 609-935-6000  ;

Extension 4455 4 Month March 1985 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 0 2 0 18 0 3 'O 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 Pg. 8,1-7 R1 8504220079 850331" hM ADOCK O

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l OPERATING' DATA REPORT Docket No. 50-311

Date. April 10,1985

. Telephone 935-6000

. Completed by J. P. Ronafalvy Extension 4455 Operating Status l

1. Unit Name- Salem No. 2 Notes

' 2. . Reporting Period March 1985 -

3. -Licensed Thermal Power (MWt) 3411

- 4. Nameplate Rating (Gross MWe) ITT6

5. Design Electrical Rating (Net MWe) TITY

. 6. Maximum Dependable Capacity (Gross MWe)lllT

7. Maximum Dependable Capacity (Net MWe) Illli 8.. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason __

N/A

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 i

r. 11. Hours in Reporting Period 744 2160 30385
12. No. of' Hrs. Reactor was Critical 0 0 15094.6
13. Reactor Reserve Shutdown Hrs. 0 0 3533.6
14. Hours Generator On-Line 0 0 14612.1
15. Unit Reserve Shutdown Hours 0 0 0

~ 16. Gross Thermal E1:ergy Generated -

(MWH) 0 0 43727036

17. Gross Elec. Energy Generated (MWH) 0 0 14277650
18. Net Elec. Energy Generated (MWH) (12207) (16756) 13501080
19. Unit Service Factor 0 0 48.1
20. Unit Availability Factor 0 0 48.1
21. Unit Capacity Factor (using MDC Net) 0 0 40.2

.22. Unit Capacity Factor

'(using DER Net) 0 0 39.9

23. Unit Forced Outage Rate 100 100 41.7
' ' 24. Shutdowns scheduled over next 6 months (type, date and duration of each)

N/A'

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

4-11-85 26.sUnits in Test Status (Prior to Commercial Operation) :

Forecast Achieved Initial Criticality 6/30/80 8/2/80 Initial Electricity 9/1/80 6/3/81 Commercial ~ Operation 9/24/80 10/13/81 8-1-7.R2 i

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UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-311 REPORT MONTH March 1985 Unit Name- Salem No.2 Date April 10,1985 J.P. Ronafalvy Telephone 609-935-6000 Completed by 4455 Extension Method of Duration Shutting _ License .

Cause and Corrective Type Hours Reason Down Event System Component Action to No. Date 1 2 Reactor Report Code 4 Code 5 Prevent Recurrence Stator Windings HA GENERA Terminals Bushing 85-012 1-14 F 744 A 4 -

1 a

3 Method 4 Exhibit G 5 Exhibit 1 1 2 Reason Salem as.

F: Forced A-Equipment Failure-explain 1-Manual Instructions 2-Manual Scram. for Prepara- Source S: Scheduled B-Maintenance or Test 3-Automatic Scram. tion of Data C-Refueling D-Regulatory Restriction 4-Continuation of Entry Sheets E-Operator Training & Licensing Exam Previous Outage .for Licensee F-Administrative 5-Load Reduction Event Report G-Operational Error-explain 9-Other (LER) File H-Other-explain (NUREG 0161) l 4

4

MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-311 1 REPORT MONTH MARCH 1985 UNIT NAME; Salem 2 DATE: April 10, 1985 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

  • DCR NO. PRINCIPLE SYSTEM SUBJECT 2EC-1501 Diesel Generators Install control circuit transfer switches on the engine and generator control panels of each diesel generator to enable an operator to start the diesel generator under postulated fire and blackout condition.s 2EC-1555 Diesel Generators Revise the diesel stop circuit to prevent the operator from inadvertently opening the diesel breaker during a safeguard emergency controller (SEC) actuation.

2EC-1631 Armaflex Insulation All existing Armaflex (Various Systems) insulations on stainless steel piping and components shall be replaced with fiberglass insulation with a moisture barrier. The same is true for Armaflex insulation on non-stainless steel piping and

. components located near the bare stainless steel piping and components.

2EC-1638 Reactor Protection Rewire shunt trip coil of "A",

"B", Bypass "A" and Bypass "B" reactor trip breakers to open breakers upon a SSPS "A" and/or SSPS "B" train trip signal.

2EC-1651 Safeguard Emergency Modify cards in the 2A SEC to Controller (R130) eliminate spurious actuations of various safeguards equipment.

  • Design Change Request

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  • DCR NO. PRINCIPLE SYSTEM SUBJECT 2EC-1682 Polar Containment Revise upper limit suitch Gantry Crane protection arrangement as necessary to follow the recommendations made by Westinghouse's Nuclear Division and contained in Technical Bulletin No. NSD-TB 75-9, dated 9/15/75.

2EC-1687 Service Water For 21, 22, 23, 24 and 25SW57 valves, remove cavitation control tube bundles from all valves.

2EC-1711 Emergency Air Revise the supply fan control Conditioning circuitry so that on initiation of "outside accident-mixed air mode" from the Unit 2 Control Room Panel the EACS system for both units will be actuated (primary fan and associated dampers). If the primary fan fails to start or develops the required differential pressure, the standby fan will start following a time dalay of approximately 10 sec.

2EC-1724 Chemical & Volume Replace 2CV45 & 50 valves, Control Mark No. FA-127, with Gloise valves having the Mark No.

FA-130. Replace the piping downstream of the CV45 & 50 valves located on #21 and 22 C/SI pump casing drain line, with piping in accordance with Pipe Spec 49G and~ install a 1500# blind flange at the end of these lines. Fabricate spool pieces in accordance f

with Pipe Spec 53D to be used during maintenance on the respective pumps.

  • Design Change Request
  • DCR NO. PRINCIPLE SYSTEM SUBJECT 2EC-1785 Electrical Install new 15 volt DC power supply in 2A SEC, Install new Potter Brumfield relays in Unit 2 SEC's.

2EC-1814 Condensate Polishing Reline embedded floor drain piping using corrosion / erosion resistant material - provide necessary core bores in floor for access.

2EC-1833 Main Steam Install one valve, Mark F-55, off the drainage line between the penetration areas and the No. 22 Condenser.

2EC-1835 RVLIS Perform the field modification as per Westinghouse Procedure No. NSID-EIS-83-16. Scope of this change is under Section 5 of this procedure which includes environmental / seismic qualifications and human factors modifications.

2EC-1850 Main Steam Install additional steam stop valve hydraulic control bypass valve trouble light on control console for each of four valves21-24MS167.

2EC-1873 Containment Replacement of butyl expansion Ventilation joints at FCU discharge end for containment fan coil units Nos. 21, 22, 23, 24 & 25 with

! expansion joints made of EPDM material.

l 2ET-1881 Chilled / Service Test application of Garlock i

Water " Turbo-Star" cartridge type mechanical seal in C:iiller Condenser Recirc Pump No. 21.

  • Design Change Request
  • DCR NO. PRINCIPLE SYSTEM SUBJECT

'2EC-1898 Safeguards Equipment Install shielding around Control wiring from input relays to electronic card file of the SEC. Move line filters closer to DC power supplies.

2EC-1967 RVLIS Modify the RVLIS system using Westinghouse Procedure NSID-SIS-84-15 to upgrade the system to the current requirements.

2EC-2003 E220 DC Power System Replace existing battery 2C, consisting of 60 cells of C&D batteries model LCU-33 and rack with its equivalent replacement C&D batteries model LC-33 and reack with model RD-659.

2EC-2044 2A Diesel Generator Plug the. lower drain Lube Oil Cooler connection from the bonnet, on the return end, of the lube oil cooler for No. 2A Diesel Generator.

2SC-0314 Service Water Modify service water pump (21, 22 Pumps only) motors to allow filling of il reservoirs.

2SC-0322 Main Steam Remove the following cables from the main steam stop valves21-24MS167 & replace with high temp. wiring IMS207A;B; IMS205AA;B; IMS213E;F;G:H.

2SC-0364 Condensate Modify condensate heater drain

(#22A Circulator) and circulating water pump motors to allow filling of oil reservoirs.

2SC-0436 Service Water Revise one anchor bolt design for each service water strainer.

  • Design Change P.equest
  • DCR NO. PRINCIPLE SYSTEM SUBJECT 2SC-0966 Reactor Head Design temporary shielding in accordance with Proto-Power Management Corporation proposal #7612000-A009.

Shielding would be installed prior to stud detensioning and removed after stud tensioning completed.

2SC-1014 Steam Generator Feed Revise AC power feed to #21 and Condensate and #22 SGFP governor and speed circuitry (SA-2805C, SA-2806C, SD-2270, SD-2292) to feed only the above mentioned items. All other l non-essential equipment in these panels should be on a separate feed.

2SC-1128 Reactor. Ventilation Provide swing bolt connections to the CRDM vent fans.

2SC-1358 Containment Replace containment fan coil Ventilation unit suction expansion joints with ones of improved design.

2SC-1434 Fuel Handling Replace comb push rods, (BPRA Tool) clevis and clevis pins, retainers, etc. in accordance with instructions supplied with Westinghouse modification kit.

2SC-1435 Pressurizer Relief Install ladder, railing and Tank grating as necessary to provide safe easy access to-top of pressurizer relief tank.

2SC-1466 Fuel Handling Tools Install modification kit recently purchased from Westinghouse into the control rod drive shaft unlatching tool.

  • Design Change Request
  • DCR NO. PRINCIPLE SYSTEM SUBJECT 2SC-1488 Service Water Provide permanent engineering design to satisfy Operations Department test SP (O) 4.0.5V leak rate check for 21 &

22SW51 and 21 & 22SW79 valves.

  • Design Change Request

MAJOR-PLANT MODIFICATIONS DOCKET NO.: 50-311 REPORT MONTH MARCH 1985 UNIT NAME: Salem 2 DATE: April 10, 1985 COMPLETED BY: J. Ronafalvy TELEPHONE: ' 609/339-4455

  • DCR NO. 10CFR 50.59 SAFETY EVALUATION 2ET-1501 This change improves plant safety by making vital power available much sooner during certain postulated fir plus blackout conditions. Failure of the Control Transfer Switch may cause the associated diesel to fail to start during a safeguards actuation. This failure is considered to be within the realm of the single failure criteria. No unreviewed safety or environmental questions are involved.

2EC-1555 This change is consistent with design philosophy which locks out all operator control of safety equipment during an SEC actuation. No additional equipment is being introduced into the design and the purpose of the equipment being modified is not being changed. No unreviewed safety or envircnmental questions are involved. l 2EC-1631 This change addresses the requirement to preclude the occurrence of stress corrosion cracking on stainlesc steel piping and components by replacing the existing armaflex insulation with fiberglass insulation. No unreviewed safety or environmental questions are involved.

2EC-1638 The installation of equipment to operate the shunt trip mechanisms on the reactor trip breakers will enhance the r operability of the reactor' trip breakers and ensure their automatic opening when required by the RPS, For additional details of this safety evaluation reference Engineering Safety Evaluation S-C-R120-CSE-241 (Safety Evaluation For Automatic Shunt Trip for the Reactor i

Protection System). No unreviewed safety or environmental questions are involved.

I 2ET-1651 This change adds electronic components to printed circuit cards in the 2A SEC to test corrective action to reduce susceptibility of certain SEC output circuitry to electronic noise. These components are CCI items equivalent ' to many of the items already present in the SEC card files. Also, the components will not affect the o

seismic qualification of the SEC nor will they malfunction in any way which is inconsistent with'the present design

, of the SEC. No unreviewed safety or environmental questions are involved.

'

  • Design Change Request

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  • DCR NO. 10CFR 50.59 SAFETY EVALUATION 2EC-1682 Installation of the new upper limit switch and other hardware on to the Polar Gantry Crane will not affect the safe shutdown of the Reactor nor will it areate any new fire hazard. There are no changes to the FSAR nor to the Tech. Specs. Implementation of this change complies with NUREG-0612, Section 51.6 requirements for upgrading cranes at operating plants. No unreviewed safety or environmental questicns are involved.

2EC-1687 Removal of cavitation control bundles from the SW57 valves will enable the valves to function without interferences by loosened tube bundles plugging with marine shells, which induce low Service Water flow. No unreviewed safety or environmental questions are involved.

2EC-1711 The modifications involved provide stop and alarm features to two independent channels. The function of having one of two fans available remains unchanged. There are no Tech. Spec. changes involved. This change will quarantee the 1/4" differential pressure in the Control Room with respect to the outdoors as required by Tech. Specs. No unreviewed safety or environmental questions are involved.

2EC-1724 The blind flange will be in accordance with the piping specification applicable to the discharge piping of the SI/ Centrifugal Charging Pumps. This piping change does not constitute a degradation in system integrity. The blind flange will climinate two potential paths of unidentified ,

leakage from the RCS. Therefore, the integrity of the RCS has been upgraded. The valve replacement corrects the Maintenance problem associated with the welded bonnet of the original valves. The new valves are designed to the system temperature and pressures and are classified as Seismic I Nuclear I valves. No unreviewed safety or

. environmental questions are involved.

2EC-1785 This DCR replaces existing components with components manufactured by a different vendor. All replacement components have been seismically qualified to IEEE 344 to the same or higher stress levels as the original equipment. No unreviewed safety or environmental questions are involved.

  • Design Change Request

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  • DCR NO. 10CFR 50.59 SAFETY EVALUATION 2EC-1814 The core boring as required by this DCR is in a non-safety related building. No unreviewed safety or environmental questions are involved.

2EC-1833 The installation of a valve to drain condensate to the atmosphere is an improvement to the station start-up operation wich in no way creates a new safety hazard. The modification takes place in the non-safety related area of the Main Steam lines. No changes to the FSAR or the Tech.

Specs are required. No unreviewed safety or environmental questions are involved.

2EC-1835 All potential, realistic failure modes have been considered but are not applicable. These changes are required to make the RVLIS fully meet the requirements of NUREG 0737. No unreviewed safety or environmental questions are involved.

2EC-1850 This change will not affect the intended function of the system. No unreviewed safety or environmental questions are involved.

2EC-1873 This change replaces the flexible expansion joint, between the fan section to the discharge of the ring duct header of the CFCU, with a better joint. The new joint will be better able to withstand the environmental conditions inside the Containment after an accident. A hole or tear in the joint will not impair the Containment cooling capability since only three out of five CFCU's are required to mitigate the consequences of the design basis accident. The new expansion joint does not create any presently performed safety analysis nor does it create any new safety hazards. The EPDM rubber used in the new joints has been "hypalon" jacketed to minimize the fire hazard of the material and improve its resistance to radiation degradation. No unreviewed safety or environmental questions are involved.

2ET-1881 This test of the " Garlock Turbo-stem" mechanical seal does not affect any presently performed safety analysis nor does it create any new hazards. The basis for the Tech.

Specs. remains unchanged. No unreviewed safety or environmental questions are involved.

  • Design Change Request
  • DCR . NO. 10CFR 50.59 SAFETY EVALUATION 2EC-1898 This change only involves relocation of filters and-addition of cable shielding to increase immunity to electrical transients which occ r within the' equipment.

No functional changes are being made. No unreviewed safety or environmental questions are involved.

2EC-1967 All potential, realistic failure modes have been considered but are not applicable. These changes are required to make the RVLIS fully meet the requirements of NUREG 0737. No unreviewed safety or environmental

- questions are involved.

2EC-2003 - This change replaces the existing 2C battery arrangement -

with an equivalent safety related Class 1E battery and battery rack. No unreviewed safety or environmental questions are involved.

2EC-2044 Installation of a plug in the lower drain connection of

. the Lube Oil Cooler does not effect the cooler's performance. The plug will be "steaked" so it can not vibrate loose and it will also be coated with a film of Belzona Molecular Metal to assure a leak free joint, as

. well as protect the plug from salt water. No unreviewed safety or environmental questions are involved.

2SC-0314 The change in the upper oil fill piping will not affect the operation of the motor. No unreviewed safety or environmental questions are involved.

2SC-0322 This DCR results in the upgrading of cables to MS167 Main Steam stop valves improving reliability and service. No unreviewed safety or environmental questions'are involved.

2SC-0364 The change in the upper and lower oil fill piping will not affect the operation of the motors. No unreviewed safety or environmentcl questions are involved.

,_ 2SC-0436 This DCR allows the repair of strainer housing. It does

, not. weaken structural integrity of the building or jeopardize the safe shutdown of NSSS equipment. No unreviewed safety or environmental questions are involved.

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  • . Design Change Request 1

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  • DCR NO. 10CFR 50.59 SAFETY EVALUATION 2SC-0966 This DCR involves the installation of lead wool blankets in support of Reactor Vessel stud detensioning (during Modes 5 and 6). The shielding adds 4 tons to the reactor vessel lift rig lift. WCAP 10167 contains the stress report for the RV Lift Rig. Per this report, the shielding will not cause the components to exceed 1/3 of >

their yield strength nor 1/5 of their ultimate strength.

Therefore, the RV Lift Rig design will continue to meet the NUREG 0612 guidelines. The mounting brackets for the shielding, are bolted to the RV Lift Rig legs and will remain in place after the shielding is removed. The method of fastening the brackets to the legs does not affect the integrity of the legs nor alter the load carrying capability of any member. During Modes 1 thru 4 the brackets are not loaded and therefore there is no danger of these brackets becoming a missile hazard during a seismic event. This DCR does introduce plastic material into the Containment, however, the material will be removed priior to start-up and there is fire extinguishing equipment in the area (as well as tours by fire watches) ..

No unreviewed safety or environmental questions are involved.

2SC-1014 This change adds a separate feed for some SGFP instrumentation. The instrumentation function (s) do not change. No unreviewed safety or environmental questions are involved.

2SC-1128 The brackets installed will be used to hold flex connections adjacent to the CRDM. Implementation of this DCR does not affect the safe shutdown of the plant. No unreviewed safety or environmental questions are involved.

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  • Design Change Request

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  • DCR NO. 10CFR 50.59 SAFETY EVALUATION 2SC-1358 This change replaces the flexible expansion joint, between the fan section to the filler section of the CFCU, _ with a better joint. The new joint will be better able to withstand the environmental conditions inside-the Containment after an accident. A hole or tear in the joint will not impair the Containment cooling capability since only three out of five CFCU's are required to mitigate the consequences of the design basis accident.

The new expansion joint does not create any presently performed safety analysis nor does it create any new safety hazards. The EPDM rubber used in the new joints has been "hypalon" jacketed to minimize the fire hazard of the material and improve its resistance to radiation degradation. No unreviewed safety or environmental questions are involved.

2SC-1434 This modification includes replacement of the original comb rods on the 3PRA handling tool with those of-a heavier gauge. The modification does not reduce the margin of safety as defined in the Tech. Specs. The DCR does not increase the probability of occurrence or the consequences of any accident previously evaluated in the FSAR. No unreviewed safety or environmental questions are involved.

2SC-1435 This DCR adds a small platform and a ladder to provide safe access to the top _ of the Pressurizer Relief Tank. No existing systems are to be modified. No unreviewed safety or environmental questions are involved.

2SC-1466 This modification includes material changes to eliminate galling on the stainless steel sleeve of the Control Rod Driver Shaft Unlatching Tool. The modification does not reduce the margin of safety as defined in the Tech.-Specs.

The DCR does not increase the probability of occurrence or the consequences of any accident previously evaluated in the FSAR. No unreviewed safety or environmental questions are involved.

2SC-1488 This DCR provides a more dependable means of leak rate

-testing Service Water valves 21 & 22SW51 and 21 & 22 SW79.

The improved design will ensure the integrity of the valves and that they function as per design. The CS piping, cut in the field, will be lined with Belzona along with the new CS fittings to ensure their integrity. No unreviewed safety or environmental questions are involved.

  • Design Change Request

PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG 1

SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION

, 8503240165 l SMD 2 22 SJ54

' FAILURE DESCRIPTION: VALVE WILL NOT CLOSE ELECTRICALLY OR BY MANUAL OPERATION. PLEASE REPAIR.

, CORRECTIVE ACTION: REMOVED DEBRIS FROM ACTUATOR

8503220580

, SMD 2 2CV244 FAILURE DESCRIPTION: THE VALVE STILL DOES NOT WORK PROPERLY THIS W/O '

WAS WRITTEN TO COVER THE FAILED RETEST OF W/O # 8406254751 CORRECTIVE ACTION: DISASSEMBLED AND INSPECTED VALVE. REASSEMBLED WITH NEW GASKET 8503210118 SMD 2 LEAK IN SEAL TABLE ROOM FAILURE DESCRIPTION: DURING SERVICE PRESSURE LEAK EXAM OF UNIT 2 CONT. LEAKAGE WAS NOTED ON THE TABLE IN THE SEAL l TABLE ROOM. PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: REMOVED HIGH PRESSURE FITTINGS AND INSTALLED NEW NUTS AT LOCATION L-5, E-11, H-13

8503170485 SMD 2 21MS168, 3-WAY STM PORT i

FAILURE DESCRIPTION: 21MS168, THE 3-WAY LIMITORQUE SELECTOR VALVE FOR THE MSIV STM. PORT VALVES IS BLOWING STEAM BADLY.

LOOKS LIKE IT IS COMING FROM A FURMANITE FITTING.

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PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: FURMANITED VALVE, PERMANENT REPAIRS TO BE MADE NEXT OUTAGE

q SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8503170051 SMD 2 22 SW PUMP FAILURE DESCRIPTION: PUMP.HAS A PACKING LEAK, NO ADJUSTMENT LEFT.

MAINT. DEPT PLEASE REPACK PUMP.

CORRECTIVE ACTION: REPLACED PUMP 8503170060 SMD 2 24 SW STRAINER FAILURE DESCRIPTION: STRAINER HAS A BAD PACKING LEAK. NO ADJUSTMENT LEFT. MAINT DEPT PLEASE REPACK.

CORRECTTVE ACTION: REPACKED STRAINER ,

8503140292 SMD 2 SUPPLY FAN ,

FAILURE DESCRIPTION: ROUGHING FILTER IS CLOGGED UP, PLEASE REPLACE CORRECTIVE ACTION: REPLACED BLANKET ROUGHING FILTER (FOLIO #90-005) 8503150018 SIC 2 2SW311 OVERPRESS. CONT FAILURE DESCRIPTION: CONTROLLER FOR 2SW311 APPEARS TO HAVE A CLOGGED INSTRUMENT LINE. I&C DEPT PLEASE INVESTIGATE CORRECTIVE ACTION: CLEANED BLOCKED ORIFICE IN PA-9638Z TRANSMITTER AND CALIBRATED

SALEM UNIT 2.

WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8503120381 SMD 2 2A DIESEL GENERATOR FAILURE DESCRIPTION: TROUBLESHOOT CAUSE OF CR-1 RELAY CONTACTS NOT CLOSING ON START SIGNAL. (RELAY COIL DOES NOT OPERATE)

CORRECTIVE ACTION: REPLACED CR-1 RELAY ALSO RECAL. 2PD6 445,6446,6447, 6448. I&C CHECKED ISTG SPEED RELAY FOUND SAT.

RECAL. 2STL SPEED RELAY FOUND AT 170 RPM RESET 200 RPM 8503080532 SMD 2 2B DIESEL GEN FAILURE DESCRIPTION: FUEL INLST TO HEADER CAP SCREW IS BROKEN.

PLEASE REPLACE CORRECTIVE ACTION: CHANGED BOLT TO AIR VALVE 8503100029 SMD 2 22RH19 FAILURE DESCRIPTlON: PASSING FLOW THROUGH LEAK OFF LINE, PLEASE REPAIR CORRECTIVE ACTION: REDUCED LEAD OFF LINE TEMP 45 DEG. TIGHTENED DOWN ON PACKING NUTS INITIAL TEMP. 150 DEG.

8503100118 SIC 2 21 IODINE REMOVAL UNIT FAILURE DESCRIPTION: DAMPER 2CBV25 REMAINS OPEN WITH FAN OUT OF SERVICE, PLEASE REPAIR CORRECTIVE ACTION: REPAIRED DEFECTIVE SOLENOID VALVE SV-925.

i SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8503110024 SIC 2 DORIC PT 521 FAILURE DESCRIPTION: DORIC POINT 521 AND COMPUTER POINT T0935A ARE FAILING. POINT IS FOR 22 RHR MOTOR INBOARD BEARING PLEASE INVESTIGATE AND REPAIR CORRECTIVE ACTION: CLEANED TC WIRES AT BACK OF COMPUTER AND IN RELAY ROOM. COMPUTER AND DORIC READ OKAY 8503110156 SMD 2 21 BF19 FAILURE DESCRIPTION: BONNET LEAKING CORRECTIVE ACTION: REM, BONNET, REPLACED BONNET, GASKET AND RETORQUED BONNET NUTS 8503070154 SMD 2 2CU277 FAILURE DESCRIPTION: BODY TO BONNET LEAK.

CORRECTIVE ACTION: DIS. VLV, REPLACED BONNET NUTS, STUDS AND GASKET REASSEMBLED 8503030071 SMD 2 HYD RES LEAK 22 S/G SNBR FAILURE DESCRIPTION: VISUAL EXAMINATION PER M11B REVEALED THE STRAINER AFTER THE RESERVOIR OUTLET VALVE 22HR904 (RES TO SNUBBER 90057-21A) IS DRIPPING HYDRAULIC FLUID.

PLEASE INSPECT AND REPAIR. ANY QUESTIONS. CONTACT ,

C.J. CONN'R EXT 4511 CORRECTIVE ACTION: INSTALLED GASKET

SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8503010607 SMD 2 23 RCP OIL LVL ALARM FAILURE DESCRIPTION: ALARM IS UP WITH OIL LEVELS SAT. MAINT DEPT PLEASE REPAIR CORRECTIVE ACTION: FOUND BAD PC CARD FOR OHAC-22 REPLACE CARD LIGHT CLEARED 8503020050 SMD 2 21 F.C.U.

FAILURE DESCRIPTION: INVESTIGATE 21 CONTAINMENT FAN COIL UNIT HIGH SPEED OPERATION CORRECTIVE ACTION: REPLACED OPERATIh? MECHANISM ON THE TIE-BREAKER.

ARRANGED WIRING TO MAINTAIN PROPER ROTATION OF LOW AND HIGH SPEED ,

0099163667 SIC 2 23 CHILLER RECIRC AUTO VL FAILURE DESCRIPTION: 23 SW102 AND 23 SW93 ARE NOT OPERATING CORRECTLY. THIS IS A MODE 4 REQUIREMENT CORRECTIVE ACTION: REBUILT SV-595 0099163683

  • SMD 2 22 CS PMP RM COOLER BKR FAILURE DESCRIPTION: WITH BKR CLOSED, GET NO INDICATION IN CONTROL ROOM AND RM COOLER DOES NOT RUN. MODE 4 REQUIREMENT CORRECTIVE ACTION: REBUILT MOTOR PART

SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 0099163624 SMD 2 21SW99 FAILURE DESCRIPTION: 21SWO99 CHILLER DISCHARGE CHECK VALVE FAILS ITS 4.0.5-V-SW-2 TEST. THIS IS A MODE 4 REQUIREMENT CORRECTIVE ACTION: VALVE WAS BELZONA WITH RUBBER, NEW GASKET WAS MADE, REASSEMBLED AND PUT BACK INTO PLACE.

REWORK ON WO 0099159937 0099163659 SIC 2 21SW129 AIR SOLENOID VA FAILURE DESCRIPTION: THE AIR SOLENOID VALVE TO 21SW129, APPEARS TO NEED REPLACING, AS IT IS EXTREMELY HOT AND CANNOT

  • BE MADE TO CHANGE POSITION. THIS IS A MODE 4 REQUIREMENT CORRECTIVE ACTION: ' REBUILT SOLENOID VALVE, BENCH TESTED, AND REINSTALLED 0099163608 SMD 2 2RllA FAILURE DESCRIPTION: THE CHANNEL IS FAILED CORRECTIVE ACTION: FOUND SETPOINTS CONDITION INCORRECT. RE-ENTERED SETPOINTS TO CLEAR FAULTY CONDITION 0099163454 SMD 2 AIR DUCT FAILURE DESCRIPTION: AIR DUCT FROM CFCU RING DUCT BEHIND ELEVATOR ACCESS PORT MISSING CORRECTIVE ACTION: INSTALLED NEW ACCESS DOOR (18X12) FAB. IN HAP'S SH OP

SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 0099163527 SMD 2 IL AND SL CYL OIL LEAK FAILURE DESCRIPTION: PLEASE REPAIR THE FUEL OIL LEAK ON IL AND SL CYLINDERS CORRECTIVE ACTION: MADE BOLT AND INSTALLED IN IL CYL.

0099163373 SIC 2 21SW49 & 21SW305 FAILURE DESCRIPTION: 21 SW HDR OVERPRESSURIZATION VALVES 21SW49 AND 21SW305 WILL NOT OPERATE AT THEIR APPROPRIATE SETPOINT. PLEASE REPAIR. MODE 4 ENTRY REQUIREMENT CORRECTIVE ACTION: VALVE WAS CONTROLLING 10 LBS UNDER SETPOINT CONTROLLER WOULD NOT CALIBRATE. REPLACED CONTROLLER CALIBRATED AND CHECKED OPERATION ,

0099163390 SIC 2 #24 RCP SEAL LEAK-OFF FAILURE DESCRIPTION: NO LOW RANGE SEAL LEAK-OFF INDICATION CORRECTIVE ACTION: PC BOARD WAS LOOSE. FIXED.

0099163411 SMD 2 25SW PUMP FAILURE DESCRIPTION: BAD PACKING LEAK, OPERATOR CANNOT TIGHTEN CORRECTIVE ACTION: REPLACED PACKING 0099163276 SMD 2 22SW76 VALVE HANDWHEEL FAILURE DESCRIPTION: 22SW76 (22 CFCU OUTLET VALVE) HAS A BROKEN HAND-WHEEL. PLEASE REPAIR .

CORRECTIVE ACTION: REWELDED NEW PIECE ON ORIGINAL HAND WHEEL

SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 0099163209 SIC 2 RX HEAD VENTS IND FAILURE DESCRIPTION: 2RC41 SIMULTANEOUS OPEN/ CLOSED INDICATION 2 RC42 NO INDICATION ALL HEAD VENTS ARE CLOSED CORRECTIVE ACTION: ADJUSTED INDICATOR SWITCHES AND FUNCTIONALLY CHECKED OPERATION 0099163241 SIC 2 2VC2 FAILURE DESCRIPTION: WILL NOT OPEN - NEED OPERABLE FOR MANUAL SI TEST CORRECTIVE ACTION: FOUND AIR SHUT OFF AT VALVE ,

0099005409 ,

SMD 2 2A DIESEL FAILURE DESCRIPTION: DIESEL WOULD NOT START CORRECTIVE ACTION: REBUILT TRIP LEVER AND RACK DOGS 0099005492 SMD 2 22 AUX FEED PUMP FAILURE DESCRIPTION: PUMP SEIZED AND DAMAGED CASING AND ROTATING ELEMENT.

CORRECTIVE ACTION: REPAIR AS NECESSARY 0099005344 SMD 2 2A EMERG DIESEL FAILURE DESCRIPTION: INVESTIGATE FAILIIPE TO RESTART AFTER 24 HOUR RUN ON 850309 CORRECTIVE ACTION: ALIGNED FUEL RACK TO FUEL PUMPS INSPECTED AIR START PISTON, INSPECTED LINKAGE AS PER DCR 85-3423

~

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 2 MARCH 1985 SALEM UNIT NO. 2 The period began with the second refueling / turbine outage in progress.

Main Generator replacement work continues. Electrical and mechanical modifications were completed for adaptation of the General Electric Generator. Final Generator alignment was completed. Exciter final alignment has been completed. The Lube Oil System flush, Stator Water flush and Seal Oil flush were initiated and completed. The Main Generator gas leak test was successfully completed. The Main Generator has been pressurized with hydrogen in preparation for operation. The Turbine was placed on its turning gear. A vacuum in the Condensers has been established. Reactor Coolant System fill and vent was initiated and completed. Phase A and Phase B Containment Isolation Tests have been completed. MSR work has been completed. On 3/16/85, with the completion of all DCR work required for Modes 4 and 3 operation and the completion of Containment cleanup, heatup of-the Unit commenced. At 0340 hours0.00394 days <br />0.0944 hours <br />5.621693e-4 weeks <br />1.2937e-4 months <br />, the Unit entered Mode 4 (l.ot shutdown) and on 3/17/85 at 1611 hours0.0186 days <br />0.448 hours <br />0.00266 weeks <br />6.129855e-4 months <br />, the Unit entered Mode 3 _ (hot standby) .

On 3/22/85, No. 22 Auxiliary Feed Pump was found to be inoperable.

The pump was replaced and final alignment and testing of the pump is in progress. Also, two (2) conoseals were found to be leaking. The Unit was brought to Mode 5 (cold shutdown) to allow repairs. With the completion of repairs to the conoseals, Mode 4 (hot shutdown) operation was reached on 3/31/85, at 1038 hours0.012 days <br />0.288 hours <br />0.00172 weeks <br />3.94959e-4 months <br />.

F 1 I

REFUELING INFORMATION DOCKET NO.: 50-311 COfiPLETED BY: J. Ronafalvy UNIT NAME: Salem 2 DATE: April 10, 1985 TELEPHONE: 609/935-6000 EXTENSION: 4455 Month March 1985

1. Refueling information has changed from last month:

YES X NO

2. Scheduled date for next-refueling: September 6, 1986 3.- Scheduled date for restart following refueling: November 16, 1986
4. A) Will Technical Specification changes or other license amendments be required?

YES NO Not determined to date B) Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO X If no, when is it scheduled? August 1986

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

August 1986 if required

6. Important licensing considerations associated with refueling:

NONE

7. Number of Fuel Assemblies:

A) Incore 193 B) In Spent Fuel Storage 140

8. Present licensed spent fuel storage capacity: 1170 Future spent fuel storage capacity: 1170
9. Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity: March 2003 8-1-7.R4

O PSEG $

Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station April 10, 1985 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 In Compliance with Section 6.9, Reporting Requirements for the Salem Technical Specifications, 10 copies of the following monthly operating reports for the month of March 1985 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Safety Related Work Orders Operating Summary Refueling Information Sincerely yours, J. M. Zupko, Jr.

General Manager - Salem Operations JR:sbh cc: Dr. Thomas E. Murley Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Director, Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Enclosure ,

8-1-7.R4 l The Energy People

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