ML18101A342

Monthly Operating Rept for Oct 1994 for Salem Generating Station Unit 1.W/941114 Ltr

ML18101A342
Person / Time
Site:	Salem
Issue date:	10/31/1994
From:	Hagan J, Morroni M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9411230312
Download: ML18101A342 (12)

Text

e PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station November 14, 1994 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 1 DOCKET N0.: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 October 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, RH:vls Enclosures C Mr. Thomas T. Martin Regional Administrator USNRC, Region I 631 Park Avenue King of Prussia, PA 19046 The power is in your hands. r2 2

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PDR ADOCK 05000272 95-2189 REV 7-92 R PDR

~RAGE DAILY UNIT POWER L~

Docket No.: 50-272 Unit Name: Salem #1 Date: 11/10/94 Completed by: Mike Morroni Telephone: 339-5142 Month October 1994 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1082 17 1047 2 1108 18 1116 3 1105 19 1105 4 1111 20 1110 5 1095 21 1108 6 1105 22 1105 7 1092 . 23 1093 8 1101 24 1105 9 1107 25 1117 10 1097 26 1102 11 1090 27 1118 12 997 28 1105 13 1020 29 1114 14 931 30 1109 15 952 31 1115 16 1051 P. 8.1-7 Rl

OPERATING DATA REPORT Docket No: 50-272 Date: 11/10/94 Completed by: Mike Morroni Telephone: 339-5142 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period October 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 None.

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 745 7296 151993

12. No. of Hrs. Rx. was Critical 745 5123.6 100255.6

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 745 4404.3 96292.2

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2500171. 2 14625686.4 305398000.4

17. Gross Elec. Energy Generated (MWH) 841270 4508110 101044080

18. Net Elec. Energy Gen. (MWH) 807705 4242426 96179979

19. Unit Service Factor 100 60.4 63.4

20. Unit Availability Factor 100 60.4 63.4

21. Unit Capacity Factor (using MDC Net) 98.0 52.6 57.2

22. Unit Capacity Factor (using DER Net) 97.2 52.2 56.8

23. Unit Forced Outage Rate 0 31.8 21.6

24. Shutdowns scheduled over next 6 months (type, date and duration of each)

Refueling outage scheduled to start 4-8-95 and last 60 days.

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

N A.

8-1-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH OCTOBER 1994 DOCKET NO. :~5o--0-,.-=27~2--=---

UN IT NAME: Salem #1 DATE: 11-10-94 COMPLETED BY: Mike M<>rroni TELEPHONE: 339-5142 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 6 TO PREVENT RECURRENCE 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 DOCKET NO: 50-272 MONTH: OCTOBER 1994 UNIT NAME: SALEM 1 DATE: 11/10/94 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.

1. Discrepancy Evaluation Form (DEF)

DES-90-01600 Component DE-CB-CB.AN-0049 (Q), Open Item 13 - No document has been found to confirm that testing was performed to determine extent of hydrogen generation. - At the present time, Section 6.2.5.1.5 of the Salem UFSAR discusses the extent of hydrogen generation from a particular paint, (Phenoline 305 made by Carboline) being exposed to gamma radiation (ionizing radiation). The NSSS (Westinghouse Electric Corporation) stated that their original test results done in the early 1970's showed no hydrogen was produced from exposing this paint to gamma radiation. Westinghouse, however, was unable to locate the original test document that outlined the test results quoted; and, PSE&G has no copy of the test or its results.

Therefore, Westinghouse has since written a letter to PSE&G stating that no elemental hydrogen would be generated from exposing the paint in question to gamma radiation. Technical Specification Sections 3/4.6.1.6.1 -

Containment surfaces and 3/4.6.4 - Combustible gas control mention nothing about hydrogen being produced from paint exposed to gamma radiation. Furthermore, as no hydrogen would be produced if the paint were exposed to ionizing radiation, there can be no impact to the margin of safety as defined in the basis for the Technical Specifications.

(SORC 94-077)

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: OCTOBER 1994 UNIT NAME: SALEM 1 DATE: 11/10/94 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162

2. Design Change Packages (DCP) lEE-0085, Pkg. 1 Change the Section I code boundary of the feed water system from the BF3 Valves to the BF19 valves. This will bring the boundary in line with Section 1, Figure PG-58.3.1 "Code Jurisdictional limits for Piping Drum type Boilers",

and the PSE&G commitment to the State of New Jersey.

This change affects the non-safety related portion of the Feedwater System. It changes the boundary of the Section I, boiler external pipe jurisdiction. It makes no other changes. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 94-077) lEC-3370, Pkg. 1 Replace the existing low pressure copper-nickel tube bundles ofMSR llW, 12W, 13W (Component ID #IMSE8, IMSEI 1, and IMSE14, respectively) with new stainless steel tube bundles. Modify the L.P. MSR bundle channel cover and MSR shell man-ways to accept a spiral wound gasket in lieu of a welded diaphragm seal. Replace six main steam coil drain tank high level dump valves (valve Nos.

1 IRD 36, 12RD36, 13RD36, 1 IRD3, 12RD3 and 13RD3) with leak tight shut-off valves. Valve material is Chrome-Moly. Install stainless steel strainers and support upstream of the RD-3 and RD-36 valves. Replace the piping from the strainer to condenser with stainless steel piping, and high pressure 4th pass drain pipe with Chrome-moly piping. The only failure modes of the proposed low pressure tube bundles are leakage and rupture. There are no other known failure modes. This is the same as for the present bundles.

Any low pressure tube rupture accident will be very remote after the proposed tube bundles are installed, due to improved L.P. tube bundle mechanical design. and improved stress and corrosion resistance. Any small loss of steam would be directed to the L.P. turbine, and then to the condenser. The affects of leakage or a tube rupture on the

H1CFR50-.59 EVALUATIONS DOCKET NO: 50-272 MONTH: OCTOBER 1994 UNIT NAME: SALEM 1 DATE: 11/10/94 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 reactor and its associated margins of safety are not addressed in the basis of any Technical Specification. As such, there are no requirements of the MSR system imposed by the Technical Specifications and no reduction in the margin of safety. (SORC 94-077) lEC-3323, Pkgs. 1&2 Service Water Large Bore Pipe Replacement - Service Water Intake Structure Bays 1 & 3 - These DCPs were initiated to replace Service Water Piping in Service Water Intake Structure Bays 1 & 3. It involves the replacement of carbon steel cement or coal tar lined pipe with 6%

Molybdenum Austenetic Stainless Steel pipe. This modification upgrades the Service Water System pipe material. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 94-078) lEC-3322, Pkgs. 1&2 Service Water Large Bore Pipe Replacement - Auxiliary Building - Headers 11&12 - These DCPs were initiated to replace Service Water Piping in the Auxiliary Building -

Headers 11&12. It involves the replacement of carbon steel cement or coal tar lined pipe with 6% Molybdenum Austenetic Stainless Steel pipe. This modification upgrades the Service Water System pipe material. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-078) lEC-3336, Pkg. 1 Steam Generator Thermal Sleeve Upgrade - This project involves modification of the existing Steam Generator feedwater nozzle thermal sleeves and adjacent piping at all four of the Salem Unit 1 Steam Generators. The modifications are required to eliminate cracking in the weld counterbore area which occurred twice in the present configuration. The modified corifiguration employs a single piece tuning fork forging fabricated from SA 508 Class 2 material. The design eliminates the thickness discontinuity

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: OCTOBER 1994 UNIT NAME: SALEM 1 DATE: 11/10/94 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 (Cont'd) ___ _

11::::=1::::::::::f:::::::::::::::n1:::::::]::::=::r:I:::::i:]::::1:::::]:]:))]::l::::::::::1::]:]:::::]:::::::=:*:::::::::,:::::::]::::::=:===::]:::]:::::§-1:::::=:::=::::,::::::::I::,::::::r::::::::]:::::]::::::::::::r:t]::r:::::1:::::r:::::11 in the nozzle to piping weld, completely eliminates the reducer to elbow weld, and moves the elbow to pipe weld past the stratified zone. The design also provides erosion/corrosion protection of the feedwater piping and the existing thermal sleeve. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-080)

3. Temporary Modifications (T-Mods)

T-Mod 94-085 Temporary.Movement ofBlowdown Analyzer Drains Receiver - The purpose of this T-Mod is to temporarily move the Blowdown Analyzer Drains Receiver to allow for passage oflarge spool piping required during accomplishment ofDCP lEC-3322 Pkg. 2. There are no Technical Specifications applicable to the drain receiver tank or its function. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 94-078)

T-Mod 94-083 Control Air IA Header Jumper Installation - This modification installs a mechanical jumper in place of containment isolation valve 11CA330. UFSAR Section 6.2.4 describes that in order to prevent the release of radioactivity to the outside environment in the event of a LOCA, there are two barriers at each penetration, on inside containment and one outside containment. Since this T-Mod will be implemented in Modes 5, 6 or undefined, this requirement does not apply. UFSAR Section 15 was also reviewed and the proposed modification will not increase the probability of a There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 94-081)

ldCFR50:59 EVALUATIONS DOCKET NO: 50-272 MONTH: OCTOBER 1994 UNIT NAME: SALEM 1 DATE: 11/10/94 CO:l\1PLETED BY: R. HELLER TELEPHONE: 609-339-5162

4. Safety Evaluations MRS-2.4.2-GEN38 Steam Generator Shot Peening - Shot peening of the hot leg side steam generator tubes is being proposed at Salem Generating Station during lRl 1 and 2R8. The shot peening will be performed by Westinghouse under their field procedure MRS-2.4.2-GEN38. The intent of the shot peening process is to increase the margin of resistance in the areas of the tubes within the tub sheet transition region that are susceptible to primary water stress cracking corrosion (PWSCC). The shot peening operation includes the shot peening of each tube through the tubesheet area, the transition area, and an increment of the unexpanded tube above the top of the tubesheet. The margin of safety can be increased for tubes which are not degraded. Corrosion testing has shown that the shot peening process will significantly retard the development of PWSCC in uncracked tubes. The margin of safety will not be affected in tubes which have already experienced PWSCC at the tube expansion transition. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 94-080)

A-O-ZZ-NSE-0838-0 Design Change Exclusion Zone for Various Artificial Island Buildings - The purpose of this evaluation is to identify structures and justify their position as being outside the scope of the Nuclear Jurisdiction (NAP 8 does not apply to modifications performed in these structures) as described in the Exclusion Zone Technical Standard. The facilities and equipment installed in these facilities do not have an impact on the Operating Point, Analysis Assumption, Setpoint or Acceptance Limits as defined in the bases for any Technical Specification and has no interaction with facilities or equipment that has an impact on the Operating Point, Analysis Assumption, Setpoint or Acceptance Limits as defined in the bases for any Technical Specification. There is

ldCFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: OCTOBER 1994 UNIT NAME: SALEM 1 DATE: 11/10/94 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-080)

A-0-VARX-NSE-0727-1 Equivalent Replacement and Document Update Generic Evaluation - This generic safety evaluation is prepared to address plant part and component changes due to obsolescence, unavailability, and subsequent document update of the Salem and Hope Creek SARs. The replacement of equivalent plant parts and/or components authorized by this generic evaluation, will meet or exceed all the original operating characteristics, specifications and design requirements, as documented in the required Equivalency Evaluation. Since no design specifications will be degraded, the NRC's prescribed operating limits that provide sufficient operating range such that the acceptance limits are not exceeded during plant operations and analyzed transients, will not be affected. Since the acceptance limits will not be exceeded, there is no impact on the margin of safety. (SORC 94-081)

REFUELING INFORMATION DOCKET NO: 50-272 MONTH: OCTOBER 1994 UNIT NAfv.lE: SALEM 1 DATE: 11/10/94 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 MONTH : OCTOBER 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_A_

lfno, 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 ofFuel 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

SALEM GENERATING STATION MONTfilY OPERATING

SUMMARY

- UNIT 1 OCTOBER 1994 SALEM UNIT NO. 1 The Unit began the period operating at 100% power and continued to operate at essentially full power throughout the entire period.