ML20072T184

Monthly Operating Rept for Mar 1991 for Hope Creek Generating Station,Unit 1

ML20072T184
Person / Time
Site:	Hope Creek
Issue date:	03/31/1991
From:	Hagan J, Zabielski V Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9104180002
Download: ML20072T184 (15)

Text

m: _,_

l ., l . -1' O PSEG Public Service Electric and Gas Company P.O. Box 230 Hancocks Bridge, New Jersey 08038 Hopo Creek Generatin0 Station l

April 12, 1991 U .~ S . - Nuclear Regulatory Commission Document Control Desk Washington,-DC 20555 1 l

Dear Sir 1 MONTHLY OPERATING REPORT HOPE CREEK GENERATION STATION-UNIT 1:

DOCKET'NO.-50-354' In; compliance with:Section 6.9, Reporting Requirements for the i Hope Creek Technical. Specifications, the operating statistics for' March are being forwarded to you with the- -

-summary of changes, tests,;and~ experiments for March 1991 pursuant.to the requirements of:-10CFR50.59(b).

Sincerely yours,

k. J . - agan Genernl-Manager.--

' Hope Ct%$k Operations-g h RAR:ld' Attachments'-

.C -Distribution 9104180002 910331 /

PDR ADOCK 05000354  !/

R PDR

]3 J l The Energy People  ;

m o n gwnnt

., _ . . _ . . . . . - . . . . . - - . . - . . . _ . . . . . ~ , . _ , . _ . . _ . . . , , . . . . . , _ . . . . . . . . _ . , . ..---..-.....,--,._e.... ,.,<--c ,-c,

_ . _ . _ _ _ . . . .m__ _.

'. i INDEX NUE ER SECTION OF PAGES Average Daily Unit Power Level. . . . . . . . . . . 1 Operating Data Report . . . . . . . . . . . . . . . 2 Refueling Information . . . . . . . . . . . . . . . 1 Monthly Operating Summary . . . . . . . . . . . . . 1 Summary of Changes, Tests, and Experiments. . . . . 8 l

l l

l l

1 I

i .-

I AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-354 UNIT lione Creek DATE 4/12/91 COMPLETED BY L Zabielski TELEPHONE (609) 339-3506 MONTH March 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. A 17. 221

2. A 18. 19LO,

3. 408 19. 1Q11

4. $12, 20, 1221

5. 1Q3_2, 21. 1Q21

6. 1Qff 22. 1Qs2

7. 1931 23. 1Q11

8. 1Q&2 24. 1Q1Q 9.- 1077 25. 1Qs2

10. 1922 26. 1Q1A

11. .LQ21 27. 1Qjf.

12, 1Qs1 28. 1Q5A

13. 1Q11 29. 1064

14. 1063* 30. 1951

15. J.063* 31, 1Q2.1

16. 1Qfa cDue to an error in recording the meter readings, the exact average daily power level for March 14 and 15 is unknown. The listed averages for those two days represents the average of the two-day total.

._.____A - -_ -

-..o t; e e i OPERATING DATA REPORT DOCKET NO. 50-354 UNIT Hooe-Creek

^

-DATE' 4712/91 COMPLETED BY V. Zabielski~

TELEPHONE (609) 339-3506 OPERATING STATUS-

1. _ Reporting Period' March -1921 Gross-Hours in Report Period 2AA

3. . Currently Authorized-Power Level-(MWt) 3293 Max. Depend.-CapacityJ(MWe-Net) . 1031 DesignxElectrical Rating (MWe-Net) 1067 l L3 . Power Level to which restricted (if'any) (MWe-Net) None  !

4.- Reasons)for restriction (if any)

This Yr To Month. Data Cumulative

5. 'No. of hours reactor was critical 713.8 859.8 30,641.3.

4

6. Reactor reserve shutdown: hours Da 2x2 ExQ-

,l Hours generator on line 698.0 778.7 30.071.8

-8. Unit reserve. shutdown; hours _ 929 A19 gin L

9.- Gross thermal energy generated. 2,195,189 :2,296,733 94,839,140'

--(MWH) J u

31,380',253

~

10.LGross electrical _ energy _733,330 - 758,580

. generated . (MWH) - -

-11. Net electrical energy l generated. 704.994 711,135 29,967,819' s (MWH)-

L za2; Reactor-service factor 95.9 39.8 81.7 l

l} 13.' Reactor availability factor. 95.9 39.8 81.7 L

!14.[UnitLservice. factor- 93.8 36.1 80.2 L15.iUnit availabi'lity' factor 93.8 .36,1 80.2

=16.? Unit capacity 'f actori (using MDC) 91.9 31.9 77.5 17., Unit capacity factor 88.8 30.9 74.9:

(Using Design-MWe)

~ 18. - Unit? forced outage rate

~

A12 21.3 itQ

'19. Shutdowns scheduled over next 6 months'(type, date,-& duration):-

- None

20. If_ shutdown at-end of' report period, estimated date of start-up:

N/A t s

! OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-354 UNIT Hope Creek DATE 4/12/91 COMPLETED BY V. Zabielski TELEPHONE (609) 339-350'6 MONTH March 1991 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F= FORCED DURATION REASON REDUCING CORRECTIVE NO. DATE S= SCHEDULED (HOURS) (1) POWER (2) ACTION / COMMENTS 5 3/1 F 46 A 4 Continuation of Outage to Repair H2 Leak on Main Generator 6 3/16 F 0 A 5 Power Reduction to Repair Condenser Tube Leak Summary

4 REFUELING INFORMATION DOCKET NO. 50-354 UNIT Hope Creek DATE 4/12/91 COMPLETED BY S. Hollinasworth TELEPHONE (609) 339-1051 4 MONTH March 1911

1. Refueling information has changed from last month:

Yes X No

2. Scheduled date for next refueling: 9/5/92

3. Scheduled date for restart following refueling: 11/3/92

4. A. Will Technical Specification changes or other license amendments be required?

Yes No X B. Has the reload fuel design been reviewed by the Station Operating Review Committee?

Yes No X If no, when is it scheduled? Dot currently scheduled

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

6. Important licensing considerations associated with refueling:

- Amendment 34 to the Hope Creek Tech Specs allows the cycle specific operating limits to be incorporated into the CORE OPERATING LIMITS REPORT; a submittal is therefore not required.

7. Number of Fuel Assemblies:

A. Incore 764 B. In Spent Fuel Storage (prior to refueling) A2s C. In Spent Fuel Storage (after refueling) 760

8. Present licensed spent fuel storage capacity: 4006 Future spent fuel storage capacity: 4006

9. Date of last refueling that can be discharged July 22, 2007 to spent fuel pool assuming the present licensed capacity:

HOPE CREEK GENERATING STATION MONTHLY OPERATING

SUMMARY

MARCH 1991 At the beginning of March, Hope Creek remained shutdown to repair a Main Generator Hydrogen Seal. The Generator was synchronized at 10:00 PM on March 2nd, On March 16th, power was reduced to repair a condenser Tube leak. The unit operated for the remainder of the month without shutting down or experiencing any other reportable power reductions. At the end of the month, the unit completed its 29th day of continuous power operation.

Y .

6 j

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION MARCH 1991

The following Design Change Packages (DCP's) have been evaluated to determine:

1. If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or

2. If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or

3. If the margin of safety as defined in the basis for any technical specification is reduced.

The DCP's did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. The DCP's did not change the plant effluent releases and did not alter the existing environmental impact. The Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

s .

i QgE Description of Desian Chance Packace 4EC-1024/02 This DCP added two stairways from the existing catwalk at elevation 77' 5" to the top of the torus. Each set of stairs includes a platform and a landing. The stairways will provide a safe for of access.

4EC-3111/05 This DCP replaced two Class HXC, epoxy lined carbon steel Service Water spool pieces with piping Class HZC, 6% Molybdenum stainless steel. The new material is more corrosion /crosion resistant.

4EC-3112/01 This DCP replaced 14 Class HXC, epoxy lined carbon steel Service Water spool pieces with piping class HZC, 6% Molybdenum stainless steel. This DCP also mortar lined carbon steel replaced 10 Class Service Water HGC[ng Screenwash Suction Line Travell spool piecessteel.

stainless with piping Theclass newHZC,in material more6% Molybdenum corrosion / erosion resistant.

4EC-3112/05 This DCP replaced two Class HXC, epoxy lined carbon steel Service Water spool pieces with piping Class HZC, 6% Molybdenum stainless steel. The new material is more corrosion / erosion resistant.

4EC-3112/06 epoxy lined carbon This steelDCP replaced Service WaterClass spoolHXC[eces p with piping class HZC, 6% Molybdenum stainless steel. The new material is more corrosion /crosion resistant. This DCP also replaced Safety Auxiliaries Cooling System balancing valves with aluminum bronze butterfly valves.

4EC-3112/09 This DCP modified the Station Service Water System by adding a manual butterfly isolation valve, a manual drain valve, and a standpipe. It also epox replaced a Class Service Water HXC,iece.y spool p lined All ofcarbon the newsteel material is made with piping Class HZC, 6% Molybdenum stainless steel. The new material is more corrosion / erosion resistant.

4EC-3112/11 This DCP diverted the Station Service Water System water flow to the Cooling Tower Basin and to the Cooling Tower Bypass Line. This modification permitted the draining of the Cooling Tower during the modifications to the Service Water System Return to Cooling Tower Piping.

4EC-3112/12 epoxy lined This DCP carbon replaced steel Serviceseven WaterClass spoolHXC,ieces p with piping Class HZC, 6% Molybdenum stainless steel. The new material is more corrosion / erosion resistant. It also replaced two butterfly valves to improve the isolation and shutoff capability.

I

r '.

QQ2 Description of Desian Chance Packa_gg 411M-0522 This DCP completed the site grading and paving in the southwestern portion of the !! ope Creek yard.

The final design is very close to the original design, the differences being minor grading changes.

r .

The following Temporary Modification Requests (TMR's) have been evaluated to dntermine:

1. If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or

2. If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or

3. If the margin of safety as defined in the basis for any technical specification is reduced.

The TMR's did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor, The TMR's did not cnange the plant effluent releases and did not alter the existing environmental impact. The Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

.-.-. . - - .. - - - ~.~.- - - - - . - - . - - - .- ~ - . _ ~ . .

d' ,, .

IBB ~ pescriotion of Temocrary Modification Reauest 91-014 This TMR modified the process computer to identify 1

.the as-installed positions of the Traversing Incore 1 Probe Stationary Guide Tubes. The tubes were swapped during re-installation during the third refueling outage.

i-91-015 This TMR removed the overload heaters from the breakers for the Reactor Water Cleanup Discharge to Condenser Valve and the Reactor Water Cleanup Discharge to Equipment Drain Valve. Removing the overload heaters from the breakers will prevent the valves from inadvertently opening during an Appendix R fire.91-016 This TMR unpinned a sway strut hanger on the High.

Pressure Coolant Injection Steam Supply Line to prevent the strut from bending or breaking during the High Pressure Coolant Injection System Steam l Line warmup. The TMR was removed when the steam line warmup was completed. .91-017 This 1MR provided an alternate flowpath for the offgar. Hydrogen Analyzer's Sample Return Line by conne! ting the existin Condeiser Return Line.g sample return to theThe existing sample return line was plugged, making the hydrogen analyzers inoperable until a flowpath was made available.91-018 This.TMR installed a 1" PVC Acid Injection Line to the Makeup Domineralized Water Regenerative Waste Tank. The original line has disintegrated the PVC is more resistant to the chemical reaction,than the original material.-

f l.

I L

L_-

1 l

r

O a The following procedure revision has boon ovaluated to dotormino:

1. If the probability of occurrence or the consequences of an accident or-malfunction of equipment important to safety previously evaluated in the safety analysis report may be increasod; or

2. If a possibility for an accident or malfunction of a difforont type than any evaluated previously in the safety analysis report may be created; or

3. . If the margin of safety as defined in the basis for any technical specification is reduced.

The procedure revision did not create a now safoty hazard to the plant nor did it affect the safo shutdown of the reactor. The proceduro revision did not change the plant offluent roloasos and did not alter the existing environmental impact. The Safety Evaluation determined that no unreviewed safety or environmental questions are involved.

L I 1

l l

l:

1 ..- -- ._ _ - _ . . _. -. -

Procedure Revision Descriotion of Proc _edure Revision l NC.NA-AP.ZZ-0025(Q) This procedure supersedes SA-AP. ZZ-025 'Q) ,

Rev. O which is referenced in several places :.n the UFSAR. This Safety Evaluation identifies where SA-AP.ZZ-025(Q) is referenced so those paragraphs can be revised.

i l

1 l

3