ML20085E486
| ML20085E486 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/31/1995 |
| From: | Lyons D, Reddemann M Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9506160550 | |
| Download: ML20085E486 (12) | |
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iO PSEG
.-.s Public Sorvice Electric and Gas Company P.O. Box 236 Hancocks Bndge. New Jersey 08038 Hope Creek Generating Station June 15,1995 U. S. Nuclear Regulatory Commission Document Control Desk Washington,DC 20555
Dear Sir:
MONTHLY OPERATING REPORT HOPE CREEK GENERATION STATION UNIT 1 DOCKET NO. 50-354 In compliance with Section 6.9, Reporting Requirements for the Hope Creek Technical i
Specifications, the operating statistics for May 1995 are being forwarded to you with the summary of changes, tests, and experiments that were implemented during May 1995 pursuant to the requirements of10CFR50.59(b).
i Sincerely yours,
]
. h 2) }lW Mark eddemann General Manager -
Hope Creek Operations
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Attachments C Distribution 9506160550 950531 PDR ADOCK 05000354 At R
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INDEX NUMBER SECTION OF PAGES Average Daily Unit Power Level.......................................................................... I 7
t Operating Data Report..............................
.....2 Refueling Information.............................................................................1 Monthly Operating Summary............................................................... I Summary of Changes, Tests, and Experiments............................................. 6 4
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DOCKET NO.: 50-354 UNIT: Hooe Creek DATE: 6/15/95 COMPLETED BY:
D. W. Lyons TELEPHONE: (609) 339-351 AVERAGE DAILY UNIT POWER LEVEL MONTH MAY 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 10.1%
l'i 1031 0
2 1Q11 18 1Q13 3
1049 19 1038 4
1Q11 20 841 5
1047 21 1023 6
1049 22 1036 7
10]s 23 1Q42 8
1QLQ 24 10)_3, 9
241 25 1032 10 1011 26 1040 11 1047 27 1040 12 1047 28 1025 13 1045 29 1029 1
14 1046 30 1036 15 1Q4J 31 1028 I
16 1045 i
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DOCKET NO.: 50-354 i
UNIT: Hooe Creek DATE: 6/15/95 j
COMPLETED BY:
D. W. Lyons j
TELEPHONE: (609) 339-351 1
OPERATING DATA REPORT OPERATING STATUS 1
1.
Reporting Period May 1995 Gross Hours in Report Period 24.4 2.
Currently Authorized Power Level (MWt) 3221 f
Max. Depend. Capacity (MWe-Net)
.LO11 Q
Design Electrical Rating (MWe-Net) 1067 3.
Power Level to which restricted (if any) (MWe-Net)
Nons 4.
Reasons for restriction (if any)
This Month Yr To Date Cumulative 5.
No. of hours reactor was critical 744.0 3463.6 63399.5 6.
Reactor reserve shutdown hours 0_0 M
M 7.
Hours generator on line 744.0 3442.0 62445.4 8.
Unit reserve shutdown hours QS Q&
M 9.
Gross thermal energy generated (MWH) 2424577 11163812 199578158 10.
Gross electrical energy generated (MWH) 800633 JJ28982 66156648 11.
Net electrical energy generated (MWH) 767051 3574351 63227667 12.
Reactor service factor 100.0 216 316 13.
Reactor availability factor LQQA 216 Bis 14.
Unit service factor 100.0 21Q 34 1 15.
Unit availability factor 100.0 2.LQ 8_ 41 1 16.
Unit capacity factor (using MDC) lQQS 212
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17.
Unit capacity factor (using Design MWe) 96.6 22J 80.0 18.
Unit forced outage rate QA LQ 42
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l 19.
Shutdowns scheduled over next 6 months (type, date, & duration):
j Refueling Outage, November 11,1995,30 days j
20.
If shutdown at end of report period, estimated date of start-up:
N/A l
DOCKET NO.: 50-354 UNIT. Hone Creek DATE: 6/15/95 COMPLETED BY: D. W. Im TELEPHONE: (609) 339-3517 OPERATING DATA REPORT UNIT SIIUTDOWNS AND POWER REDUCTIONS MONTH MAY 1995 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F= FORCED DURATION REASON REDUCING CORRECTIVE NO.
DATE S= SCHEDULE (IIOURS)
(1)
POWER (2)
ACTION / COMMENTS 1.
NONE r
4 DOCKET NO.: 50-354 l
UNIT: Hope Creek l
DATE: 6/15/95 COMPLETED BY: D. W. Lyons
- ELEPHONE: (609) 339-351 REFUELING INFORMATION MONTH MAY 1995 1.
Refueling information has changed from last month:
Yes X
No 2.
Scheduled date for next refueling:
11/11/95 3.
Scheduled date for restart following refueling:
12/10/95 4A. 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 Station Operating Review Committee (SORC)?
Yes No X
If no, when is it scheduled? October 25.1995 5.
Scheduled date(s) for submitting proposed licensing action:
Not requirei
)
6.
Important licensing considerations associated with refueling:
N/A 7.
Number ofFuel Assemblies:
A. Incore 764 B. In Spent Fuel Storage (prior to refueling) 1;L40 C. In Spent Fuel Storage (after refueling) 1422 8.
Present licensed spent fuel storage capacity:
4006 Future spent fuel storage capacity:
4006 9.
Date oflast refueling that can be dischary,ed 5/3/2006 to spent fuel pool assuming the present hcensed capacity:
(EOCl3)
(Don allow for full-core off-load)
(Assumes 244 bundle reloads every 18 months until then)
(Does nel allow for smaller reloads due to improved fuel)
4 DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 6/15/95 COMPLETED BY: D. W. Lyons (y TELEPilONE: (609)339-3517 MONTIILY OPERATING
SUMMARY
MONTH MAY 1995 The Hop Creek Genereing Station remained on-line for the entire month and operated at essentially 100% power for the month of May 1995. At the end of the month the unit had been on-line for 65 days. The following occurred during May 1995:
A marsh fire under the Keeney (5015) Electric Transmission line caused that line to trip out of service. The disturbance created by the tripping of the Keeney Line resulted in a Reactor runback to 78% power at 2341 hours0.0271 days <br />0.65 hours <br />0.00387 weeks <br />8.907505e-4 months <br /> on May 8,1995. Based on grid stability curves, the System Operator requested Hope Creek go to and remain at 70% power until the line was returned to service. The unit was returned to full power at by 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on May 9,1995.
Scram timing, control rod swaps, feedwater heater maintenance and the weekly turbine valve surveillances were performed between 00:01 hours on May 20,1995 and 09:00 hours on May 21,1995.
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DOCKET NO.: 50-354 UNIT: Hooe Creek DATE:.6/15/95 COMPLETED BY: p. W. Lyonj TELEPHONE: (609) 339 351
SUMMARY
OF CHANGES TESTS, AND EXPERIMENTS FOR TIIE IIOPE CREEK GENERATING STATION MONTH MAY 1995 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 dermed 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 efIluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.
Desien Channes Summary M Safety Evaluations 4HE-00051 - REROUTE DIESEL BUILDING HVAC DRAINS This configuration e
change makes minor changes to the condensate drain piping from the Diesel Building HVAC units. This change will allow removal of copper impunties from the wastewater by sending the water through the neutralization tank prior to returning it to the normal waste stream. If a failure occurs, the water will flow to the floor drain system where it will be processed as waste. UFSAR Figures 9.4-1 and 9.4-15 and text in UFSAR Section 9.3.3.2.2.b will have to be revised to reflect this change.
Therefore, this DCP does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve any Unreviewed Safety Question.
- 4HE-00147 FIRE EXTINGUISHER INSTALLATION IN ELEVATOR MACilINE ROOMS This configuration change install eight carbon dioxide fire extinguishers in the elevator machine rooms at Hope Creek. These fire extinguishers are required by the New Jersey Administrative Code. The fire protection program currently addresses fire in the elevator machine rooms utilizing existing hose stations as the primary fire fighting feature.
Therefore, any malfunction of these extinguishers is of no consequence to the fire protection program. These fire extinguishers are consistent with the existing carbon dioxide fire extmguishers provided in the station and as discussed in UFSAR Section 9.5.1.2.13. These fire extinguishers will have to be added to UFSAR Figures 9.5-2,9.5-3 and 9.5-7.
Therefore, this DCP does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve any Unreviewed Safety Question.
Procedure Summary M Safety Evaluation
- HC.CH-EO.SH-0001(O)- POST ACCIDENT SAMPLE PANEL OPERATION The nitrogen pressure regulator setting is being changed from 120 psig to 100 asig to conform with General Electric's design specification and operating procedares. T1is will prolong the life of the pneumatic components supplied from this header. The reference to 120 psig found in UFSAR Section 9.3.2.3.2, Item 11, is believed to be typographical error because the several GE documents including design specification and the operating manual as well as the vendor manual for the diaphragm operated valves explicitly state the 100 psig setting.
Therefore, this change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve any Unreviewed Safety Question.
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Temporary Modifications Summary of Safety Evaluations e 95-027 - JUMPER 1 A-K-403 IHGH MOTOR TEMPERATURE SENSOR This temporary modification installs an electrical jumper across the high motor temperature switch inp circuitry in the I A-K-403 IE Panel Room Chiller until a replacement part can be installed. The chiller motor temperature will still be monitored by the CRIDS computer which will ;enerate an alarm in the control room to alert the operators to take proper action shou'd a high temperature condition occur. This high temperature trip is provided for machine protection only and does not affect the ability of the chiller to perform its intended function. The switch is identified in UFSAR Figure 9.2-15.
Therefore, this Temporary Modification does not increase the probability or conseguences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.95-030 - OPENING 1" BYPASS VALVES AROUND 6" BACIGVASH VALVE This proposal will open the 1" bypass valves, IEAHV-446/447, around the strainer backwash valves, IEAHV-219A/C, for the purposes of evaluating if this configuration will reduce the amount of valve cycling occurring during river silt and debris excursions. The heavy spring sitt and debris prevalent in the Delaware River has consistently caused excessive backwash operations in order to maintain the proper differential pressure across the strainer. This cycling has caused the motor duty cycle to be challenged and the thermal overloads to trip.
Opening the 1" bypast lines will cause a continuous backwash which will reduce the strainer differential pressure.
Should debris and silt become excessive, the normal backwash logic will still function as designed. The Service Water pumps are rated for 16,500 GPM at 150 Feet TDH, opening the 1" bypass valve will not impact the rated flow to the SACS Heat Exchangers or operating characteristics of the pump.
Therefore, this Temporary Modification does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
e 95-032 - JUMPER 1 AK400 CONTROL ROOM CHILLER HI BEARING OIL TEMPERATURE TRIP This temporary modification installs an electricaljumper across j
the high bearing oil temperature trip switch on the I AK-400, Control Area Chiller until a replacement part can be installed. The chiller motor temperature will still be monitored both locally by equipment operators on rounds and by the CRIDS computer. The CRIDS computer will generate an alarm in the control room to alert the operators to take proper action should a high temperature condition occur. This high temperature trip is provided for machine protection only and does not affect the ability of the chiller to perform its intended function. The switch is identified in UFSAR Figure 9.2-15.
Therefore, this Temporary Modification does not increase the probability or conseguences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question
Deficiency Reports Summary of StittE Evaluations e 950509099 - LEAK RlEPAIR OF 1AFV-045 This Deficiency Report addresses the leaking of I AFV-045, tu 6A Feedwater Heater Drain Line Valve. This is a normally closed valve but is leaking past its seat causinji ncreased radwaste. To stop the leakage i
l the valve will be injected on the upstream of t w seat with a sealant. Precautions will be taken to prevent injection of the sealant into the shell side of the feedwater heater or the feedwater stream. However, the affect of this sealant on the system has been analyzed and found to be acceptable. This repair does not affect any equipment that is important to safety nor are there any previously evaluated accidents that are applicable.
Therefore, the disposition of this Deficiency Report does not increase the probability or l
consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question e 9(0119204 - USIC-AS-IS FOR DEGRADED ELECTRIC HEATING COILS IN C ERS SUPPLY TAN This Defici Report addresses the 33% degradation of the electric heating coils in the CERS supp fan, I A-VH407. The degradation was due to overheating. This fan supplies filtere and tempered air to the Lower Relay Room, control equipment mezzanine, cable spreadinj; room, inverter rooms and HVAC equipment rooms. A portion is, also, suppliec to both Q and non-Q battery rooms through Battery Room Duct Reheat coils. The original capacity of the heaters was 100 Kw, tne reduced capacity will be 67 Kw UFSAR Table 9.4-1 lists the heating ca pacity of this system as 341,300 BTU /hr. The reduced capacity will be 228,670 BTUhr. The i
system is designed to warm 5000 cfm of 5*F air to 60 F. The reduced capacity of the i
heaters will still provide sufficient heat input to warm the unheated outside air from 5 F air to 47 F. When mixed with the recirculated 60*F air, the final temperature will be 58.9 F.
Of all the areas to which this system supplies air, only the battery electrolyte has a specified minimum temperature and it is 60 F. Because this temperature is entical the battery rooms have Duct Reheat coils designed to take the 60 F air and heat it to 77 F, well above the minimum temperature. Similar equipment rooms in other HVAC systems at Hope Creek have minimum temperatures specified at 40 F. The 47 F capability of the system under the coldest temperatures would still be able to maintain this temperature.
Therefore, the disposition of this Deficiency Report does not increase the probability or conseguences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question 1
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1 a-Qthat Summarv giSafety Evaluations
'JFUR CHANGlC ' 95 Dl'ESEL FUEL OIL TANK SETTLING TIME e
Nrr ATIOh Eaci diesel engine ins two fuel oil storage tanks associated with it. Per -
section 9.5.4.2.1 of the UFSAR, one fuel oil storage tank is designated as a fill tank, and the other fuel oil storage tank is designated as the diesel engine supply tank. In order to provide adequate time for sediment to settle after the last fuel od delivery, a ten hour settling time is required before switching tank designations. Currently, this ten hour settling time is required when fuel oil level drops below 22,300 gallons prior to filling.
This ciange to the UFSAR lowers the 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> settling time initiation point from 22,300 gallons to 19,000 gallons. Disturbance of any accumulated sediment would be a result of the turbulence introduced during filling of the tank and would be proportional to the axial t
velocity of the plume of fuel oil as it impinges on the sediment at the bottom of the tank.
The change in axial velocity at the bottom of the tank when filled from the lower level is insignificant. This change will better allow the operators to conduct the standby diesel generator 24-hour run while operating at power. This change will result in no adverse effects on the standby diesel generator fuel oil storage system, nor the standby diesel generators.
Therefore, this UFSAR change does not increase the probability or consequences of an i
accident previously described m the UFSAR and does not involve an Unreviewed Safety Question.
l UFSAR CHANGE 95 PORTABLE FIRE EXTINGUISHERS This UFSAR i
e change notice clarifies the appicability of UFSAR Section 9.5.1.2.13 for portable fire I
extinguishers and revises Section 9.5.1.5 to reflect use of NFPA 10 for guidance only.
UFSAR section 9.5.1.2.13 indicates that portable fire extire Shers are provided m accordance with NFPA 10 and OSHA regulations and recommendations. The Class A fire fighting capability is provided by stancpipes and hose stations. However, there is acditional discussion in UFSAR section 9.5.1.2.13 concerning Class A fire fighting i
capability being provided by stand pipes and hose stations which conflicts with the requirements of NFPA 10 which requires fire extinguishers with a Class A rating regardless of the availability of stand payes or other fire suppression systems. A second deviation concerns the maximum trave distance to a fire extinguisher.. Deviations to NFPA standards are to listed in UFSAR Section 9.5.1.6. This item is not discussed there.
The lack of portable fire extinguishers with Class A ratings does not effect the ability to extinguish a fire of this type smce the type of fire extinguishers installed are considered i
acceptable for use on a Class A hazard ifused in the early stages of fire development. If a fire were to develop to a more deep seeded fire, fire hose stations which are provided throughout areas that contain, or could present a fire exposure to, safety-related equipment would be utilized. Our arrangement of fire suppression equipment is in consistent with BTP CMEB 9.5-1.
Exceeding the recommended travel distance to the installed fire extinguishers does not effect the ability to extinguish a fire. Travel distances are established in NFPA 10 on the assumption the building occupant is responsible for fire suppression. This is not the case at Hope Creek.
Therefore, the arrangements of portable fire extinguishers which results in deviations from NFPA 10 does not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire since adequate means for fire suppression are provided to ensure fire suppression within the area that the fire originated. Therefore, this UFSAR change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
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