ML18100B205

Monthly Operating Rept for June 1994 for Salem Generating Station Unit 1.W/940714 Ltr

ML18100B205
Person / Time
Site:	Salem
Issue date:	06/30/1994
From:	HAGAN J J, HELLER R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9407180211
Download: ML18100B205 (10)

Text

• PuGlic Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station July 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 June 1994 are being sent to you. RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions 10CFR50.59 Evaluations PORV or Safety Valve Challenges Operating Summary Refueling Information Sincerely yours, cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 The _Energy 9407180211 940630 PDR ADOCK 05000272 c:, *nr..: R 1-, j'Oi 95-2189 (10M) 12-89

.ERAGE DAILY UNIT POWER LE .. Docket No.: 50-272 Unit Name: Salem #1 Date: 07/10/94 completed by: Mike Morroni Telephone:

339-2122 Month June 1994 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 1009 2 0 18 997 3 0 19 1048 4 272 20 1035 5 672 21 892 6 945 22 826 7 1010 23 486 8 985 24 403 9 943 25 0 ( 10 604 26 0 11 0 27 162 12 0 28 809 13 0 29 993 14 0 30 1069 15 129 31 16 957 P. 8.1-7 Rl

• OPERATING DATA REPORT

• Docket No: 50-272 Date: 07/10/94 Completed by: Mike Morroni Telephone:

339-2122 Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period June 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

12. 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) 17. 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 720 608.15 0 472.85 0 1289928 411540 382073 65.7 65.7 48 47.6 29 Year to Date 4343 2236.23 0 1726.55 0 5828832 1578850 1443303 39.8 39.8 30 29.8 50.7 cumulative 145441 97368.25 0 93614.39 0 296601146 98114820 93380856 62.8 62.8 56.6 56.2 21. 9 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. 8-1-7.R2 NO. DATE 0850 6/01/94 F 1058 6/10/94 F 1209 6/22/94 F 1250 6/24/94 s 1 2 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 76.65 B 116.36 A 49.03 A 54.15 B Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction UNIT SHUTDOWN AND POWER REDUCTIONS 4 3 5 1 REPORT MONTH JUNE 1994 METHOD OF SHUTTING DOWN REACTOR LICENSE EVENT REPORT # -----------

cc -----------

HA -----------

HF -----------

HF 3 Method: 1-Manual 2-Manual Scram SYSTEM CODE 4 E-Operator Training & License Examination F-Administrative 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-Operational Error (Explain)

H-Other (Explain)

COMPONENT CODE 5 VAL VEX DOCKET NO. :"""'5"'"'0'°""-=27"-=2"="'" __ _ UNIT NAME: Salem #1 DATE: 07-10-94 COMPLETED BY: Mike Morroni TELEPHONE:

339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE NUCLEAR OTHER STEAM VALVES TRANSF GENERATOR CURRENT AND POTENTIAL TRANSFORMERS PUMPXX INTAKE GRATING FOULING PUMPXX INTAKE GRATING FOULING 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 -Same Source * --------------

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• 10CFR50.59 MONTH: -JUNE 1994 DOCKE.O: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-272 SALEM 1 JULY 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 A. Design Change Packages 5EC-3033 Pkg 1 lEC-3278 Pkg 1

SUMMARY

"Nuclear Services Building" -This DCP provides utility tie ins for the Nuclear Services Building being constructed as a "commercial building" in the yard area between Salem and Hope Creek Generating Stations.

The building will provide additional office space and equipment storage and lab facilities.

This DCP addresses engineering and design issues associated with utility tie ins to plant systems, including domestic water, sanitary sewer, fire protection water, fire alarm, electric power, paging, and telecommunications, as they relate to Hope Creek and Salem plant structures, systems and components.

The modified systems are not discussed in any Technical Specification and do not interface with any safety related equipment.

Therefore, the margin of safety is not reduced. (SORC 94-049) "Fuel Handling Area Ventilation Modifications" Rev. 2 -This DCP entails modifications to the Unit 1 Fuel Handling Area Ventilation System which are summarized as follows: 1.) Replace backdraft dampers 2.) Remove the inlet guide vane controls for the non safety related dampers. The vanes themselves will be retained for use in airflow balancing and will be fixed in place after balancing 3.) Replacement of the safety related exhaust fan's inlet guide vanes and pneumatic operators as well as controls.

4.) Removal of the non safety related truck bay wall mounted exhaust fan, wiring and controls.

In it's place, install a non safety related, seismically supported fixed louvre and a safety related gravity pressure relief damper which will allow outdoor makeup air to enter the building when the supply fan is off or when building negative pressure exceeds the building 2" pressure control band. However, at no

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, 10CFR50.59 MONTH: -JUNE 1994 (cont'd) ITEM lEC-1019 Pkg 1 lEC-3320 Pkg 1 time will opening. margin of Technical DOCKE.O: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-272 SALEM 1 JULY 10, 1994 R. HELLER (609)339-5162 airflow exit the building through this These modifications will not reduce the safety as defined in the basis for any Specification. (SORC 94-050) "Abandonment Of No. 12 CVCS Hold-Up Tank" -The No. 12 CVCS Hold-Up Tank experienced buckling in 1979 as the result of a partial vacuum condition.

These are three eves Hold-Up Tanks for each of the two Salem units. Vacuum breakers were subsequently installed on all of these tanks. The Design Analysis which forms part of this DCP has determined the acceptability of the abandonment in place of the No. 12 CVCS Hold-Up Tank. DCP lEA-1019 formally documents abandonment of the tank. Upon implementation of this DCP, TRIS will be revised such that the normal position of the associated valves will all be "Locked Closed". The existing level indication equipment will remain connected and active so that if liquid does seep past any of the boundary valves, alarm notification will be available at the No. 109 Panel. The abandonment of 12 eves Hold Up Tank does not reduce the margin of safety as defined in the basis for any Technical Specification. ( SORC 94-051) "Condensate

& Feedwater Systems Overpressurization Protection Installation" -The purpose of this change is as follows: 1.) To install 3/4" x 1 11 flanged safety relief valves (11 & 12BF82) on the valve bonnet of check valves 11 and 12BF2. This will involve drilling the flat plate valve bonnets and welding on a flanged pipet connection to mount the relief valves. Route the 1 11 relief valve outlet piping from relief valves 11 & 12BF82 (Elv. 114'-0") to Columns HJ-13 and G-11 respectively, then down to Elv. 100 1-6 11* six (6) pipe supports will be required for these piping runs; and 2.) To install 3/4 11 x 1" flanges safety relief valves (11, 12 & 13CN141 & 142) on the 18 11 90 degree elbows on the outlet of 12/15A, B and c low

• 10CFR50.59 MONTH: -JUNE 1994 (cont'd) ITEM lEA-1065 Pkg 1 DOCKE.O: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-272 SALEM 1 JULY 10, 1994 R. HELLER {609)339-5162 pressure feedwater heaters between valves 11, 12 & 13CN24/25 and 29/30. This will involve drilling the 18 11 elbows and welding on a flanged pipet connection to mount the relief valves. The outlet piping on relief 11, 12 and 13CN141 & 142 will not require any pipe supports.

These modifications address concerns identified in INPO Operations and Maintenance Reminder {O&MR-302) and INPO Significant Event Report {SER) 02-92. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

{SORC 94-051) "Moving of Pipe Schedule Break On Drawings" -The purpose of this change is to revise applicable plant drawings (e.g. P&IDs, Arrangement Dwgs., .... ) to move the pipe schedule breaks from the outlet of the CV-124 and CV253 valves the inlet of these valves. CV124 and CV253 act as barrier valves between safety related and non-safety related portions of the eves system. To move the pipe schedule breaks on applicable drawings to include these valves in the safety related portions would be to conform to ANS/ANSI Standards

{See N10.2a-1975/ANS-51.8 Section 2.3.3). These valves are presently being purchased as safety related/seismic class 1 (valve mark number AA-28). Also, a work history review for these valves shows that maintenance has, and continues to be, performed to safety related /seismic class 1 standards.

Shifting pipe schedule breaks to include CV124 and CV253 in safety related sections of piping will only move plant requirements in a more conservative direction.

There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

{SORC 94-051)

• 10CFR50.59 MONTH: -JUNE 1994 (cont'd) ITEM UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

SUMMARY

50-272 SALEM 1 JULY 10, 1994 R. HELLER (609)339-5162 B. Procedures and Revisions NC.NA-AP.ZZ-0024(Q)

c. Temporary Modifications TMR 93-109 "Radiation Protection Program" -This is a limited revision to clarify the scope of certain monitoring requirements, to incorporate recent NRC guidance concerning training and monitoring requirements, and to clarify certain administrative requirements.

The changes to this procedure do not relate to design criteria, specifications or operation of the fuel cladding, RCS boundary, or containment and does not address any margin of safety as defined in the bases for the Technical Specifications.

Therefore, there is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-051) "Upgrade Hoisting Capacity of the Fuel Handling Crane From 5 tons to 20 Tons" -This T-Mod is in support of DCP lEC-3252, and will install a new trolley and hoist for the removal and installation of racks. The existing trolley and hoist will be used for moving the spent fuel. This temporary modification to the fuel handling crane is to be done at the start of the rerack operation.

No welding or permanent attachments are made to the crane. No existing crane components are to be removed. This modification will not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 94-049)

SALEM UNIT NO. 1 *

• SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT 1 JUNE 1994 The Unit began the period shutdown for repairs to a pressurizer safety valve and replacement of an Individual Rod Position Indicating (IRPI) system step counter. The Unit entered Mode 2 "Startup" on June 2, 1994, and was synchronized on June 4, 1994. Power was increased to 100% at 02:14 on June 7, 1994, and was later reduced to 90% at 23:00 the same day to repair a heater drain pump. The repairs were completed on June 10, 1994, and power was being increased when a generator/reactor trip occurred due to a failed generator voltage regulator potential transformer.

The transformer was replaced and the Unit was synchronized on June 15, 1994. The Unit achieved full power on June 17, 1994. On June 17, 1994, power was reduced to 90% to repair a heater drain tank level control problem. The repairs were completed and the Unit returned to full power on June 19, 1994. Power was briefly reduced to 84% on June 21, 1994 due to high condenser back pressure.

Power was further reduced to 55% on June 23, 1994, and the Unit was taken off line on June 24, 1994, for circulating water inlet area dredging.

The dredging was completed in front of Unit 1 and the Unit was synchronized on June 27, 1994. The Unit continued to operate at essentially full power throughout the remainder of the period.

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• REFUELING INFORMATION MONTH: -JUNE 1994 MONTH JUNE 1994 UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

1. Refueling information has changed from last month: YES X NO ___ _ 2. Scheduled date for next refueling:

APRIL 8, 1995 50-272 SALEM 1 JULY 10, 1994 R. HELLER (609)339-5162

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 8-1-7.R4