ML20069M422
| ML20069M422 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/31/1994 |
| From: | Hovey R, Schmidt R, Zabielski V Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9406210356 | |
| Download: ML20069M422 (11) | |
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O PSIRG Publio Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 j
Hope Creek Generating Station 1
June 15, 1994 l
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U.
S.
Nuclear Regulatory Commission Document Control Desk l
Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT i
HOPE CREEK GENERATION STATION UNIT 1 DOCKET NO. 50-354 i
In. compliance with Section-6.9, Reporting Requirements for the Hope i
Creek Technical Specifications, the operating statistics for.May l
1994 are being forwarded to you with the summary of changes, tests, and experiments that were implemented during May 1994 pursuant to j
the requirements of 10CFR50.59(b).
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Sincerely yours, l
R.
J.
Hoveh General Manager -
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Hope Creek Operations bib JC l
Attachments t
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Distribution I
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9406210356 940531 PDR ADOCK 05000354 R
PDR y'I The Energy People v
1-
% 2173 (25V) 12 4'2 r
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i INDEX NUMBER SECTION OF PAGES Average Daily Unit Power Level.
1-Operating Data Report 3
Refueling Information.
1 l
Monthly Operating Summary.
1 Summary of Changes, Tests, and Experiments.
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OPERATING DATA REPORT DOCKET NO.
50-354 UNIT Hope Creek l
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DATE 6/10/94 COMPLETED BY V.
Zabielski U
TELEPHONE (609) 339-3506 OPERATING STATUS 1.
Reporting Period May. 1994 Gross Hours in Report Period 744 2.
Currently Authorized Power Level (MWt) 3293 Max. Depend. Capacity (MWe-Net) 2031 Design Electrical Rating (MWe-Net) 1067
]
j 3.
Power Level to which restricted (if any) (MWe-Net)
None i
4.
Reasons for restriction (if any)
This Yr To l
Month Date cumulative l
5.
No. of hours reactor was critical 621.4 2271.3 55094.3 1
6.
Reactor reserve shutdown hours 0.0 0.0 0.0 7.
Hours generator on line 591.1 2195.5 54228.0 8.
Unit reserve shutdown hours Aza 212 222 i
9.
Gross thermal energy generated 1840060 6946956 172910326 (MWH)
- 10. Gross electrical energy 610520 2314710 57278664 generated (MWH)
- 11. Net electrical energy generated 582046 2203407 54731091 (MWH)
- 13. Reactor service factor 83.5 62.7 84.4
- 13. Reactor availability factor 83,5 62.7 C4,4
- 14. Unit service factor 79.4 60,6 83.1
- 15. Unit availability factor 79.4 60.6 83.1
- 16. Unit capacity factor (using MDC) 75.9 59.0 81.3
- 17. Unit capacity factor 73.3 57.0 78.6 (Using Design MWe)
- 18. Unit forced outage rate 20.6 6.5 4.5
- 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
OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.10-354 UNIT Hone Creek DATE 6/10/94 COMPLETED BY V.
Zabielski Agf TELEPHONE (609) 339-3506 MONTH May 1994 l
METHOD OF 2
SHUTTING DOWN THE TYPE REACTOR OR F= FORCED DURATION REASON REDUCING CORRECTIVE NO.
DATE S= SCHEDULED (HOURS)
(1)
POWER (2)
ACTION / COMMENTS 1
1 5/1 S
0.0 C
5 Start-up following refueling outage.
2 5/14 S
0.0 B
5 Power reduction to support testing j
of digital feed-water system.
3 5/15 F
152.9 B
3 Automatic SCRAM l
during digital
~
feedwater testing.
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1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
,50-354 UNIT Hooe Creek DATE 6/10/94 COMPLETED BY V.
Zabielski TELEPHONE (609) 339-3506 l
MONTH May 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i
(MWe-Net)
(MWe-Net) 1.
645 17.
0 2.
_.9.12 18.
O 3.
1971 19.
O 4.
1062 20.
O 5.
19.51 21.
0 j
6.
1057 22.
523 7.
1060 23.
971 8.
1000 24, 1044 9.
1056 25.
1042 i
10.
1056 26.
1044 11.
1057 27.
1059 f
12.
1039 28.
1058 i
13.
1067 29.
1041 14.
79) 30.
1044 15.
564 31, 1048 16.
0 4
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REFUELING INFORMATION DOCKET NO.
50-354 UNIT Hope Creek 1 DATE June 10, 1994 COMPLETED BY R.
Schmidt
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TELEPHONE (609) 339-3748 i
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MONTH May 1994 1.
Refunling information has changed from last month:
Yes No X 2.
Scheduled date for next refueling:
9/16/95 3.
Scheduled date for restart following refueling:
10/31/95 4.
A.
Will Technical Specification changes or other license amendments be required?
Yes No X
B.
Has the Safety Evaluation covering the COLR been reviewed by the l
Station Operating Review Committee?
Yes No X
If no, when is it scheduled?
Not scheduled yet 5.
Scheduled date(s) for submitting proposed licensing action:
H2tscheduled yet.
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6.
Important licensing considerations associated with refueling:
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Number of Fuel Assemblies:
l A.
Incore 764 B.
In. Spent Fuel Storage (prior to refueling) 1240 C.
In Spent Fuel Storage (after refueling) 1472 8.
Present licensed spent fuel storage capacity:
4006 Future spent fuel storage capacity:
4006 9.
Date of last refueling that can be discharged 5/3/2006 to spent fuel pool assuming the present (EOC13) licensed capacity:
(Does allow for full-core offload)
(Assumes 244 bundle reloads every 18 months until then)
(Does HQt allow for smaller reloads due to improved fuel)
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HOPE CREEK GENERATING STATION MONTHLY OPERATING
SUMMARY
May 1994 Hope Creek entered the month of May at approximately 100% power.
The unit operated at full power through May 15 when the plant automatically shut down due to a problem with Feedwater Level Control.
The Plant was back on line on May 21.
As of May 31 the unit has been on line for 11 consecutive days.
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SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION May 1994 The following items 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 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor.
These items did not change the plant effluent releases and did not alter the existing environmental impact.
The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.
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Desian Chance Packace Summary of Safety Evaluation 4EC-0070:
This Design Change provides a domineralized water backflush system for the back flush and air elimination of the reactor instrument lines.
The installation of the demineralized water lines and storage carte is in the reactor building.
All installations and stored items in the reactor building are subject to the II/I criteria.
The demineralized water station that is added is not safety related and is not interconnected with any safety related systems or any system that is important to safety as described in the accident analysis.
The portable demineralized water tank and hydre pump are tools to aid in the back flush of instrument tubing.
A revision to P&ID M-18-0 and HCGS UFSAR figure 9.2.7 is required.
Therefore, this DCP does not increase the probability or consequences of an accident previously described in the SAR and does not involve any Unreviewed Safety Question.
Temocrary Modifications Summar_y of Safety Evaluation T-Mod 94-012: This Temporary Modification installed an electrical jumper across the #2 Feedwater Heater Hi-Hi Level trip switches and installed a temporary keep fill line to the low side of the level transmitters.
This modification is performed due to spurious indications during power ascension and is removed at approximately 40 % Reactor Power.
This T-Mod does not increase the probability or the consequences of an accident listed in Table 15.0-2 of the UFSAR since the worst case would be for water induction into the turbine resulting in a turbine trip.
Therefore, this Temporary Modification does not increase the probability or consequences of an accident previously described in the SAR and does not involve an Unreviewed Safety Question.
T-Mod 94-013: This temporary modification installs temporary mechanical jumpers to maintain instrument air to air actuated components in various systems supplied by the riser being repaired.
Instrument air is jumpered to itself therefore there is no new affect to other systems except for the routing of the air supply lines.
The worst case failure mode is loss of instrument air as described in the UFSAR Chapter 15.
The loss of the jumpers would be identical to a breach in the instrument air system.
Therefore the failure of the T-Mod would result in a loss of instrument air as analyzed.
The temporary hose and fittings are rated above the normal operating pressure of the system and are controlled in accordance with plant procedures.
Therefore the loss of air event is not increased.
Therefore, this Temporary Modification does not increase the probability or consequences of an accident previously described in the SAR and does not involve an Unreviewed Safety Question.
Procedure Chances:
Eummary gf Safety Evaluations HC.OP-AP.ZZ-025S(O): " Degraded ECCS Performance / Loss of NPSH" This new procedure was created to implement the concerns documented in NRC Bulletin 93-03 pertaining to Post LOCA ECCS suction strainer blockage.
This abnormal response procedure is intended to be used after the occurrence of a large break LOCA which has caused debris in the drywell to be blown into the torus.
The debris could j
subsequently collected on the ECCS suction strainers causing i
decreased suction flow to the respective pumps.
The procedure would be used in conjunction with the EOP's and in no way conflicts with or negates direction provided in those procedures.
Therefore, this Procedure revision does not increase the probability or consequences of an accident previously described in the SAR and does not involve an Unreviewed Safety Question.
Other Summary of Safety Evaluation SAR Chance Notice HCP.8-003, HCP.6-041:
This proposal changes the Hope Creek UFSAR sections 9.1.2.3.3.2.2, 9.1.2.3.3.4.2 and 9.1.2.3.3.7.2 and adds section 9.1.2.3.3.3.6.
These changes will allow the minimum temperature in the spent fuel pool to be 40*f.
The current criticality analysis for the PAR racks (par Systems l
Corp. fuel racks) is applicable for the spent fuel pool temperatures of 68*f and above.
The current criticality analysis for the Holtec racks is applicable for spent fuel pool temperatures of 40*f and above.
This proposal will change the description of the dropped assembly analysis of the UFSAR and this is a change to the facility.
In order to account for the increase in reactivity due to decrease of the water temperature from 68af to 40*f, the conclusion reached for the dropped assembly analysis has been changed.
Section 9.1.2.3.3.4.2.
has been changed to address the fact that the results of (Keff) for the dropped assembly analysis is less than the results for the " KENO" reference case (industrial standard computer code used for criticality analysis).
The original PAR calculations were used to support this conclusion.
Since the resulting Koff for the dropped assembly is less than the Keff for the KENO reference case, the dropped assembly causes no adverse reactivity effects.
Therefore, this SAR Change Notice does not increase the probability or consequences of an accident previously described in the SAR and does not involve an Unroviewed Safety Question.
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SAB Chance Notice 94-18:
Hope Creek UFSAR section 9.5.1.2.3.2, identifies a surveillance procedure be performed every 7 days by site protection to verify the Diesel Driven Fire Pump Operability.
A review of this statement indicated :
This referenced testing is considered to be in conflict with licensing commitments to NUREG 1186.
Section 9.5.1.4.2 discusses testing requirements for fire protection making this statement repetitive.
i This Change Notice is to remove the misleading and repetitive statements regarding fire pump testing from section 9.5.1.2.3.2.
This revision will not impact the basic design of the Fire Protection Systems nor modify any provisions of the Fire Protection Systems.
As a result of the evaluation of this change, t
I the SAR requirements of the Fire Protection Program such as fire l
prevention, detection, and control of fire hazards, the safeguarding of life, prevention of property damage or loss due to fire at Hope Creek remain satisfied.
Therefore, this SAR Change Notice does not increase the probability or consequences of an accident previously described in the SAR and does not involve an Unreviewed Safety Question.
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