ML20197H798

Monthly Operating Rept for Apr 1986

ML20197H798
Person / Time
Site:	Salem
Issue date:	04/30/1986
From:	Ronafalvy J, White P, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8605190291
Download: ML20197H798 (17)

Text

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-272 Unit Name Salem # 1 Date May 10,1986 Completed by Pell White Telephone 609-935-6000 Extension 4451 Month April 1986 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 16 0 P. 8.1-7 R1 h .

8605190291 860430 PDR ADOCK 0 % 2 2 R -

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OPERATING DATA REPORT Docket No.50-272 Date May 10, 1986 Telephone 935-6000 Completed by Pell White Extension 4451 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period April 1986

3. Licensed Thermal Power (MWt) 3338

4. Nameplate Rating (Gross MWe) TITU

5. Design Electrical Rating (Net MWe) 1090

6. Maximum Dependable Capacity (Gross MWe) 1124

7. Maximum Dependable Capacity (Net MWe) 1079

8. If Changes Occur in Capacity Ratings fitems 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 Restric'ivns, if any N/A This Month Year to Date Cumulative

11. Hours in Reporting Period 719 2879 77448

12. No. of Hrs. Reactor was Critical 0 1834.0 46019.4

13. Reactor Reserve Shutdown Hrs. 0 0 3088.4

14. Hours Generator On-Line 0 1763.2 44268

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 5651424 136135453

17. Gross Elec. Energy Generated (MWH) 0 1872860 45168870

18. Net Elec. Energy Generated (MWH) (4738) 1785643 42891135

19. Unit Service Factor 0 61.2 57.2

20. Unit Availability Factor 0 61.2 57.2

21. Unit Capacity Factor (using MDC Net) 0 57.5 51.3

22. Unit Capacity Factor (using DER Net) 0 56.9 50.8

23. Unit Forced Outage Rate 0 8.1 28.0

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:

5-6-86

26. Units in Test Status (Prior to Commercial Operation) :

Forecast Achieved Initial Criticality 9/30/76 12/11/76 Initial Electricity 11/1/76 12/25/76 Commercial Operation 12/20/76 6/30/77 8-1-7.R2 Page of

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UNIT SHUTDOWN AND POWER REDUCTIONS . Docket No.50-272 REPORT MONTH APRIL 1986 Unit'Namn Snlen No.1>

Date. May 10,1986 Telephone' 609-935-6000-Completed by Pell White Extension 4451 .

Method of Duration Shutting Iicense Cause.and Corrective.

Down . Event System Component Action to

.No. Date Type- Hours Reason 2 Reactor Report Code 4 Code 5 Prevent = Recurrence 1

961.0 C 1 - ZZ ZZZZZZ Nuclear Normal 386 0321 S Refueling

-o 3 Method 4 Exhibit G 5 Exhibit-1 1 2 Reason Instructions . Salem as A-Equipment Failure-explain 1-Manual F: Forced 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)

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q PAJOF PLANT MODIFICATIONS DOCKET NO.: 50-272 REPOR." MONTH APRIL 1986 UNIT NAME: Salem 1 DATE: May 10, 1986 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

• DCR NO. PRINCIPAL SYSTEM SUBJECT LED-0304 VS - Control & Relay Provide the lower electrical Room penetration area supply and return air ventilation dampers with controls to shut upon a CO 2

discharge into the lower penetration area.

lEC-0884 Cables - Conduits - Reroute various cables from Trays cable tray IC003. Cable tray IC003 has been identified as overloaded during April 1982 cable audit, DR No QA-82-146.

IEC-1304 Chem & Volume Buttwelding of the valves Control System (associated with the test-vent and drain connections along the centrifugal and reciprocating charging pump suction and-discharge lies & CVC letdown line) to header making each of them a "one-piece connection".

The second valve on all vent and drain connections shall be eliminated and replaced with short nipple and screwed cap.

1EC-1554 Diesel Generators Diesel Generator (E300) - revise' the diesel stop circuit to prevent the operator from inadvertently opening the diesel breaker during a safeguard emergency controller (SEC) actuation.

4 DCR - Design Change Request

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MAJOR PLANT MODIFICATIONS (continued) .

REPORT MONTH APRIL 1986

• DCR NO. PRINCIPLE SYSTEM SUBJECT 1EC-1779 Spent. Fuel Pool Install piping for the permanent Cooling crosstieing of both the Units 1 and 2 Spent Fuel Pool Heat Exchangers. This will allow for the cooling of the fuel in the No. 1 Unit Spent Fuel Pool by using the No. 2 Spent Fuel Cooling Heat Exchanger.-

-1EC-1999 Main Reheat & Turbine Replace turbine first stage Bypass impulse pressure transmittes PA0195 and PA0216 and mount so as to reduce vibration.

• DCR - Design Change Request i

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MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-272 REPORT MONTH APRIL 1986 UNIT NAME: Salem 1 DATE: April 10, 1986 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

• DCR SAFETY EVALUATION 10CFR 50.59 LED-0304 This design change involves the installation of cables. The cables are routed in accordance with approved procedures and will not affect any safety functions, setpoints, or safety margin. No plant process or discharge is affected by this design change. No unreviewed safety or environmental questions are involved.

lEC-0884 This design change reroutes cables to eliminate an overloaded condition. This change will not affect the operation of any safety related equipment. No plant process or discharge is affected by this design change. No unreviewed safety or environmental questions are involved.

1EC-1304 This design change increases conservatism and thereby reduces the possibility of th occurrence of cracks / breaks at the st, te]) vent futureand drain connections along the centrifugal and reciprocating charging pump suction and discharge lines and CVC letdown line. No plant process or discharge is affected by this design change. No unreviewed safety or environmental questions are involved.

lEC-1554 This design change eliminates the possibility of an operator inadvertently opening the Diesel Generator breaker from the Control Room during a blackout or accident with a blackout SEC operation. 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 system. No plant process or discharge is affected by tlis design change. No unreviewed safety or environmental questions are involved.

Design Change Request

I l UNIT 1 MAJOR PLANT MODIFICATIONS (continued)

REPORT MONTH - APRIL 1986

• DCR SAFETY EVALUATION 10CFR 50.59 1EC-1779 The permanent crosstie of the U-l Spent Fuel Pool (SFP) Cooling System with the U-2 SFP Cooling System does not increase the probability of occurrence of an accident or increase the possibility of an accident of a different type than any previously evaluated. The crosstie between the units will be utilized whenever it is determined by Engineering or Operations that the i

thermal limits of either unit were to be exceeded.

It assures that additional cooling capability is always available to either unit for maintaining their pool thermal limits to within desirable limits. The crosstie will most likely be used during every major refueling outage involving a full core discharge. To further assure that the crosstie will not pose any safety problems, the crosstie piping is of the same material grade as the existing spent fuel coolign piping. The possibility of this piping cracking and causing spent fuel pool water to damage neighboring safety related equipment is no more likely than the existing spent fuel pool pipe cracking and affecting safety related equipment (no safety related equipment in the proximity of the piping that would be affected). If in the unlikely event that this moderate energy piping were to crack the worst thing that can be conceived would be the drainage of the SFP downLto its spent fuel pool suction level at Elevation 124'. The loss of this water amounts to 4' from the pools,- taking a total of 6.35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br />. The crack would most likely be l found well before the 6.35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> (since there is a )

Control Room alarm when the SFP level reaches 28'2") elapsed and.the system isolated via four (4) 6" isolation valves. No plant process or  !

discharge is affected by this design change. No  !

unreviewed safety or environmental questions are involved.

• Design Change Request a

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UNIT 1 MAJOR PLANT MODIFICATIONS (continued)

REPORT MONTH - APRIL 1986 r" 0

• DCR SAFETY EVALUATION 10CFR 50.59 r

+ 1 .

1EC-1999 The pressure transmitters are being replaced.

because of a malfunction of the' existing -

transmitters. There is no functional change.

No plant-process or discharge is affected by this design change. No_unreviewed safety or environmental questions are involved.

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• Design Change Request n .

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1 l-I PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 WO NO UNIT . EQUIPMENT IDENTIFICATION

'8601280463 1 1A-DIESEL GENERATOR OIL LEAK L8 FAILURE DESCRIPTION: FROM FAILED RETEST WO #8506281369. THERE IS STILL j' EVIDENCE OF OIL LEAKAGE SHOWING FROM.R1 AND R4.

j CORRECTIVE ACTION: TIGHTENED UP LOOSE FITTINGS ON 8L, REPLACE CASKETS ON FUEL PUMP LINE.

8602150296 1 1B DIESEL GENERATOR 9L INJECTOR FAILURE DESCRIPTION: 9 LEFT INJECTOR LEAKS, MORE THAN ACCEPTABLE.

1 I CORRECTIVE ACTION: REPLACED COPPER GASKET ON 1R, 7R, 8R, 9R.

l 8603280037 1 1PS22 FAILURE DESCRIPTION: VALVE 1PS22 HAS FAILED ITS LEAK RATE TEST.

CORRECTIVE ACTION: REMOVED 7 RINGS OF PACKING, INSTALLED 6 RING OF CHESTERTON PACKING 6 SER, BELLEVILLE WASHER, 2 PAR'1"SER, TORQUED 2 FT. LB.

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. SALE,*kUNIT1 WO NO UNIT EQUIPMENT IDENTIFICATION 8604100628 1 LOOP 3 RX COOLANT FLOW TRANSMITTEIt FAILURE DESCRIPTION: CHANNEL SENSOR FAILED TIME RESPONSE TEST.

CORRECTIVE ACTION: CALIBRATED TIME RESPONSE AKd INSTALLED TRANSMITTER S/N-3722 IN PLACE OF 409006. IFT-436. PERFORMED EQ PROCEDURE IIC-1.4.1. 019. FOUND BOTH SS PIECES TUBING TO D/P CELL BAVING SWAGELOCK FERRULES IN'DACKWARDS (REPLACED).

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860W150455

, 1 12VC19 FAILED LRT i.

FAILURE DESCRIPTION: 12VC19 VALVE FAILED LEAK RATE TEST.

CORRECTIVE ACTION: DISASSEMBLED VALVE, POLISHED PLUG, REASSEMBLED VALVE WITH NEW GASKET, BLUE CHECKED 360 DEGREES 100%. FINISHED PACKING VALVE'WITH CHESTERTON PACKING & TORQUED TO 6 FT. LBS, ADDED NEW FLEXATALIC GASKET.

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(I SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 7

i L 8604251189 1C DIESEL WOODWARD GOV.

1 FAILURE DESCRIPTION: DURING 18 MONTH SURVEILLANCE TEST COULD.NOT ADJUST.

GOVERNOR FOR 64 Hz. SPEED ADJUST KNOB CANNOT BE L INCREASED ONLY DECREASED WITH NO EFFECT ON DIESEL j: SPEED.

CORRECTIVE ACTION: REPLACED GOVERNOR.

i l 8604070125' 1 PASS CONT.

ISOLATION VALVE ATTEMPTED TO STROKE VALVE BUT HAD PROBLEM. PLUG FAILURE DESCRIPTION:

i STEM MOVES TWICE AS FAR AS OTHER VALVES.

1 CORRECTIVE ACTION: CLEANED VALVE BONNET, AND VALVE SEAT, CLEANED VALVE PLUG AND STEM, REPACKED STUFFING BOX WITH CHESTERTON PACKING.

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SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8604170995 1 1CC113 FAILED LRT FAILURE DELCRIPTION: VALVE FAILED LEAK RATE TEST.

CORRECTIVE ACTION: POLISHED STEM AND SEAL, REPACKED WITH CHESTERTON PACKING & TORQUED TO 5 LBS & REINSTALLED VALVE.

8604171002 1 1CC215 FAILED LRT FAILURE DESCRIPTION: VALVE FAILED LEAK RATE TEST.

CORRECTIVE ACTION: POLISHED VALVE PLUG AND STEM, CLEANED BONNET, STUFFING BOX AND SEAT, REPLACED SEAT GASKET, BONNET GASKET, PACKED WITH CHESTERTON PACKING & TORQUED TO 5 FT. LBS.

8604190058 1 LWR 80 FAILURE DESCRIPTION: DIAPHRAGM IS BLOWN.

CORRECTIVE ACTION: DISASSEMBLED VALVE & REPLACED DIAPHRAGM, REASSEMBLED VALVE AND TORQUED STUDS TO 40 FT. LBS.

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E SALEM-UNIT 1 WC NO UNIT EQUIPMENT IDENTIFICATION 8604220062' l' 11SS182 FAILED LRT FAILURE DESCRIPTION: VALVE FAILED LEAK RATE TEST.

CORRECTIVE ACTION: DISASSEMBLED VALVE, INSPECTED STEM & DISC, POLISHED DISC, LAPPED DISC TO SEAT, GOT QC ON BLUE, REASSEMBLED & PACKED WITH CHESTERTON PACKING.

8604220071 1 13SS182 FAILED LRT ,

. FAILURE DESCRIPTION: VALVE FAILED LEAK RATE TEST.

DISASSEMBLED VALVE, INSPECTED STEM.& DISC POLISHED l CORRECTIVE ACTION:

DISC, LAPPED DISC TO SEAT, GOT QC ON BLUE, REASSEMBLED AND PACKED WITH CHESTERTON PACKING.

8604220097 1 12VC19 FAILED LRT FAILURE DESCRIPTION: VALVE FAILED. LEAK RATE TEST.

CORRECTIVE ACTION: DISASSEMBLED AND CHECKED VALVE FOR LEAKS, REPAIRED

' STEM AND REASSEMBLED PACKED WITH CHESTERTON PACKING AND TORQUED TO 5 LBS.

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SALEM-UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8604060022 1- C C PUMP 1 FAILURE DESCRIPTION: OUTBOARD PUMP BEARING'IS LEAKING.

CORRECTIVE ACTION: CLEANED AND FREED UP ROTATING ELEMENT OF MECH SEAL.

8603220174 1 12RH18 - RHR HX OUTLET FAILURE DESCRIPTION: NO CLOSED LIMIT INDICATION.

CORRECTIVE ACTION: ADJUSTED CLOSE LIMIT SWITCH AND VERIFIED CLOSURE-FROM CONTROL ROOM.

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SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 1 APRIL 1986 SALEM NO. 1  ;

The Unit began-the period in Mode VI (Refueling) as the sixth refueling outage continued. Work completed.this outage includes refueling, steam generator work (including sludge lancing, foreign object search and retrieval (FOSAR), and eddy current testing), leak rate testing of Type "C" Containment Isolation Valves, llE, 12E, and 13W MSR HP tube bundle replacement, the upgrade of the connectors on the Control Rod Drive Mechanisms, 13 Low Pressure Turbine inspection and Main Generator inspection and frame foot loading. On April 17, 1986 at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />,the unit entered Mode 5 (Cold Shutdown) . ON April 27,1986 at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, the unit entered Mode 4 (Hot Shutdown). On April 30, 1986 at 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br />, the unit entered Mode'3 (Hot Standby).

As the period ended, the outage remains essentially on schedule as work continues.

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REFUELING INFORMATION

~ DOCKET NO.: 50-272-COMPLETED BY: J. Ronafalvy 'W2IT NAME: ' Salem 1 DATE: May 10, 1986 TELEPHONE: 609/935-6000 EXTENSION: 4455 Month April 1986

1. Refueling information has changed from last month:

YES X NO

2. Scheduled date for next refueling: September 12,'1987

3. Scheduled date for restart following refueling: November 26, 1987-

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? August 1987

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

August 1987 if required

6. Important licensing considerations associated with refueling:

NONE

7. Number of Fuel Assemblies:

A) Incore 193 B) In Spent Fuel Storage 380

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: September 2001 8-1-7.R4

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O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating station May 10, 1986 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1-DOCKET NO. 50-272 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 April 1986 are being sent to you.

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

& 5 General Manager - Salem Operations JR:sl cc: Dr. Thomas E. Murley Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Director, Office of Management

, U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Enclosures 8-1-7.R4 The Energy People m .a in u,,e..