ML18101A290

Monthly Operating Rept for Sept 1994 for Salem Unit 2. W/941012 Ltr

ML18101A290
Person / Time
Site:	Salem
Issue date:	09/30/1994
From:	Morroni M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9410240099
Download: ML18101A290 (10)

Text

PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Saler:i Generating Station October 12, 1994 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 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 September 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 -

tions 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 Ener_a\l People 9410240099 940930 95-2189 (10M) 12-89 PDR ADOCK 05000311 R PDR

A.RAGE DAILY UNIT POWER LEVE'!

Docket No.: 50-311 Unit Name: Salem #2 Complete~ by: Mike Morroni Date: 10-10-94 Telephone: 339-5142 Month Se12tember 1994 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1 1002 17 1046 2 1045 18 1046 3 1045 19 1055 4 1060 20 1040 5 1058 21 1004 6 1052 22 150 7 1038 23 0 8 1029 24 0 9 1031

25. 0 10 534 26 0 11 332 27 0  :

)

12 899 ,..!

28 0 13 985 29 0 14 686 30 0 15 1033 31 -----

16 1018 P. 8.1-7 Rl

4t0PERATING DATA REPORT Docket No: 50-311 Date: 10/10/94 Completed by: Mike Morroni Telephone: 339-5142 Operating status

1. Unit Name Salem No. 2 Notes

2. Reporting Period September 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 i~ 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

11. Hours in Reporting Period 720 6551 113664

12. No. of Hrs. Rx. was critical 557.2 6024.9 75304.5

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 513.7 5774.8 72664.3

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1617273.6 17568859.2 180031798.6 Gross Elec. Energy Generated (MWH) 508580 5614820 76161338

18. Net Elec. Energy Gen. (MWH) 478493 5334931 72462208

19. Unit Service Factor 71.4 88.2 63.9

20. Unit Availability Factor. 71.4 88.2 63.9

21. Unit Capacity Factor (using MDC Net) 60.l 73.6 57.6

22. Unit Capacity Factor (using DER Net) 59.6 73.0 57.2

23. Unit Forced Outage Rate 28.6 10.5 21. 8

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

Refueli_ng outage scheduled to start October 14, 1994 and last 77 da s.

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

NA 8-l-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH SEPTEMBER 1994 DOCKET NO.: ~5_,0.._*""31....,1::---

UNIT NAME: Salem #2 DATE: 10/10/94 COMPLETED BY: Mike Morroni TELEPHONE: 339*5142 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION 1

NO. DATE TYPE (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 6 TO PREVENT RECURRENCE 1729 09-09*94 F 12.0 B 5 ------------ CH PUMP XX #21 STEAM GENERATOR FEED PUMP 1735 09-10-94 F 24.7 B 5 ------------ CH PUMPXX #22 STEAM GENERATOR FEED PUMP 1833 09-11-94 F 5.7 A 5 ----------- cc VAL VEX #23 GOVERNOR VALVE 1834 09*13-94 F 13.4 B 5 ----------- CH PUMPXX #21 STEAM GENERATOR FEED PUMP 1n1 09-22-94 F 1b0.8 A 1 ------------ SF MECFUN #21 CHARGING PUMP 1785 09-29-94 F 45.5 G 2 ------------ CD zzzzzz INADVERTANT VALVE CLOSURE 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-Adninistrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain) *9 esign Electrical Rating (Net MWe) 1115

6. Maximun Dependable Capacity(Gross MWe) 1149

7. Maximun Dependable Capacity (Net MWe) 1106

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:L..:..:A_ _ _ _ _ _ _ _ __

This Month Year to Date Cl.lllUlative

10CFR5'o. 59 EVALUATIONS DOCKET NO, 50-311 MONTH: - SEPTEMBER 1994 UNIT NAME: SALEM 2 DATE: OCTOBER 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 (DCPs) 2EE-0046 Pkg 1 "Circulating Water Travelling Screen Modifications" 2EE-0047 Pkg 1 The purpose of these modifications is to replace 2EE-0048 Pkg 1 the existing fish baskets in the travelling 2EE-0049 Pkg 1 screens with redesigned baskets to provide better 2EE-0050 Pkg 1 fish survivability; add additional spray nozzles 2EE-0051 Pkg 1 to the provide better coverage to the travelling scree. These modifications will also replace the existing drive motors, reducer gears and couplings with more powerful equipment for increased speed.

These modifications will not reduce the margin of safety as defined in the bases for any Technical Specification The circulating water system is non-nuclear, non-safety related and is not required to support safe shutdown of the reactor plant or maintain it in a safe condition after shutdown. The function and operation of the equipment remains the same. (SORC 94-070) 2EC-3242 Pkg 1 "Fuel Handling Building Ventilation System Upgrades.

- Rev. 3 - This DCP entails modifications to the Unit 2 Fuel Handling Area Ventilation system to eliminate or improve upon system and equipment operations problems. There will be no change to the system operating parameters as a result of these modifications. Therefore, this proposal will not reduce the margin of safety as defined in the basis for any Technical Specification. (SORC 94-070) 2EC-3238 Pkgs 1&2 "Salem Unit 2 Feedwater Heater Nos. 21(22)A, B and c Tube Bundle Replacement" - The proposed modification involves the removal and replacement of tube bundles, tube sheets, hemispherical head and shell skirt on the three (3) strings of the Salem Unit 2 first stage low pressure feedwater heaters, Nos.

21(22)A, B and c. These components are experiencing chloride pitting due to exposure to high levels of chloride intrusion from severed tubes resulting from

10CFR50.59 EVALUATIONS DOCKET NO. 50-311 MONTH: - SEPTEMBER 1994 UNIT NAME: SALEM 2 DATE: OCTOBER 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd) .

ITEM

SUMMARY

the turbine generator overspeed incident. The proposed modification does not reduce the margin of safety as defined in the bases for any Technical Specification, because the feedwater system is not addressed in the Technical Specifications or their bases. (SORC 94-074) 2EC-3260 Pkg 1 "Steam Generator Blowdown system Upgrade (Unit 2) -

This DCP modifies the Steam Generator Blowdown System as follows: 1.) Replaces steam generator blowdown valves with upgraded models; 2.) Modify piping and relocate the GB9 valves for better accessibility; 3.) Increase the size of valves GB185, GB923 and GB924 from 2 11 to 3 11 , and relocate for the reconfigured 3 11 piping; 4.) Replace existing 2 11 carbon steel piping downstream of GB923 valve with 3 11 stainless steel. Replace modified piping upstream of GB923 with 3 11 chrome-moly alloy for enhanced erosion resistance; and 5.) Replace 3" carbon steel piping at the old GB9 valve locations and in the piping riser at the new 22GB9 location with chrome-molly; and 6.) Remove redundant air panel 703-2D which is currently abandoned in place.

These changes are to improve the valve and piping reliability. These changes are all in the non-Q portion of the S/G blowdown system. Other than for improved valve design and material upgrades, all the original design requirements are being maintained.

There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-074)

B. Temporary Modifications (T-Mods)

T-Mod 94-069 "Provide Temporary Power to Bus 11 2F" during #22 SPT Outage" - The purpose of this T-Mod is to provide temporary power to Bus "2F" during the #22 SPT outage. The failure of temporary jumper cables using this T-Mod would not cause any other safety related equipment to malfunction, due to existing electrical system design features. The system design features include; breaker coordination, load flow, and electrical system separation. There is no

10CFR~0.59 EVALUATIONS DOCKET NO. 50-311 MONTH: - SEPTEMBER 1994 UNIT NAME: SALEM 2 DATE: OCTOBER 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609) 339-5162 (cont'd) .

ITEM

SUMMARY

reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-071)

T-Mod 94-070 "Provide Temporary Power to Bus "2HF" during #21 SPT Outage" - The purpose of this T-Mod is to provide temporary power to Bus "2F" during the #22 SPT outage. The failure of temporary jumper cables using this T-Mod would not cause any other safety related equipment to malfunction, due to existing electrical system design features. The system design features include; breaker coordination, load flow, and electrical system separation. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-071) *

c. Procedures S2.0P-SO.CC-0002(Q) "21 & 22 Component Cooling Heat Exchanger Operation"

- Rev. 4 - The purpose of this revision is to add steps to inform the NCO of CCHX status following liquid release. Additionally, this revisions added sections 5.2 & 5.7 for restoration of 21 & 22 CCHXs

• during SEC Mode Op III Blackout/Accident Loading per Engineering Evaluation DEF-90-01434/S-C-SW-MDC-1390, Component Cooling System Temperature Setpoints for SEC Mode III. This revision does not affect the design safety function of any system, structure or component. The reduction of the service water rate through the cc heat exchangers during recirculation phase of the SEC Mode III will increase the margin of safety, under certain postulated scenarios, by ensuring that the service water pumps have adequate NPSH available during this mode concurrent with a postulated worst case single failure. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 94-071)

D. Safety Evaluations S-C-RCS-ESE-0834 "Control Rod current Trace Frequency Change" - The proposal evaluated under this review changes the rod control surveillance test frequency that was

lUCFRS0.59 EVALUATIONS DOCKET NO. 50-311 MONTH: - SEPTEMBER 1994 UNIT NAME: SALEM 2 DATE: OCTOBER 10, 1994 COMPLETED BY: R. HELLER TELEPHONE: (609)339-5162 (cont'd)

ITEM

SUMMARY

committed to as a compensatory action following the Unit 2 control rod event that occurred in June of 1993. This change does not add, delete, modify, replace or alter any equipment that is installed in the plant or described in the UFSAR. No changes are made to the rod control system or the design basis of the rod control system. The proposal does not reduce the margin of safety as defined in the basis for any Technical Specification. All regulatory design limits and subsequent dose limits will continue to be met. The requirements of GDC 25 pertaining to the rod control system will continue to be met. The safety analyses referenced in the Technical Specification Bases are not affected and will ensure that DNB margins are maintained.

{SORC 94-075)

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 SEPTEMBER 1994 SALEM UNIT NO. 2 The Unit began the period operating at full power,and continued to operate at essentially full power until September 10, when load was reduced to 50% to change control oil filters on 21 steam generator feedwater pump {SGFP). on September 11, 1994, power was further reduced to 20% due to failure of 23 main turbine governor valve. On September 13, 1994, the Unit was returned to 100% power following completion of the repairs. On September 14, 1994, power was reduced to 50% in order to investigate an increased differential pressure problem on 21 {SGFP) control oil power unit. The Unit was restored to full power on September 15, 1994, and continued to operate at full power until September 22, 1994, when it was removed from service due to #21 charging pump vibration problems. The repairs were completed and the Unit was synchronized to the grid on September 28, 1994.

Inadvertent closure of two main steam isolation valves during power ascension on September 29, 1994, required the Unit to be manually tripped by the operators. The Unit remained shutdown throughout the rest of the period.

R'E:(;IUELING INFORMATION MONTH: - SEPTEMBER 1994

• DOCKET NO, UNIT NAME:

DATE:

COMPLETED BY:

50-311 SALEM 2 OCTOBER 10, 1994 R. HELLER TELEPHONE: (609)339-5162 MONTH SEPTEMBER 1994

1. Refueling information has change.d from last month:

YES X NO

2. Scheduled date for next refueling: OCTOBER 14. 1994

3. Scheduled date for restart following refueling: DECEMBER 29, 1994

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?: OCTOBER 94

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 556

a. 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: March 2003 8-l-7.R4