ML20245C452
| ML20245C452 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 04/17/1989 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N89-077, NLR-N89-77, NUDOCS 8904270161 | |
| Download: ML20245C452 (8) | |
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' Public Service i,
Electric and Gas Company
. Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, NJ 08038 609-339 4800 Vice President Nuclear Operatums APR 17 S89 NLR-N89077 U.
S.
Nuclear Regulatory Commission Document Control Desk l
Washington, DC 20555
-Gentlemen;
' STATION BLACKOUT COPING ANALYSIS HOPE CREEK GENERATING STATION DOCKET NO. 50-354 Public Service Electric and Gas (PSE&G) hereby submits Attachments 1 and 2 to this letter in response to the requirements of 10CFR50.63. provides the results of the coping category determination and coping analysis study performed for the Hope Creek Generating Station.
provides a detailed schedule for the completion of procedural changes identified to date.
Additionally, PSE&G will complete the modifications identified in Attachment 1 within 2 years of receipt of the notification identified in 50.63(c)(3).
If there are any questions regarding the attached, please feel free to contact me.
Sincerely, Yp te 1
Attachments
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.4 Document Control Desk 2
APR 171969 NLR-N89077 C
'Mr. C. Y. Shiraki Licensing Project Manager Mr. G. W.-Heyer Senior Resident Inspector Mr. W. T. Russell, Administrator'r Region I Mr. K. Tosch, Chief New' Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN'415 Trenton, NJ.
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ATTACHMENT 1 TO NLR-N89077 Public Service Electric & Gas Company Hope Creek Generating Station Response to Station Blackout Rule AC INDEPENDENT COPING On July 21, 1988, the Nuclear Regulatory Commission (NRC) amended its regulations in 10 C.F.R.,
Part 50.
A new section, 50.63, was
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added which required that'each light-water-cooled nuclear power plant be able to withstand and recover from a station blackout (SBO) of a specified duration.
Utilities are expected to have the baseline assumption, analyses, and related information used in their coping evaluation available for NRC review.
It also identifies the factors that must be considered in specifying the station blackout duration.
Section 50.63 requires that, for the l
station blackout duration, the plant be capable of maintaining l
f core cooling and appropriate containment integrity.
Section 50.63 further requires that each licensee submit the following j
information i
1.
A proposed' station blackout duration including a i
justification for the selection based on the redundancy and reliability of the onsite emergency AC power i
sources, the expected frequency of loss of offsite power, and the probable time needed to restore offsite power; 2.
A description of the procedures that will be implemented for station blackout events for the duration (as determined in 1 above) and for the recovery therefrom, and 3.
A list and proposed schedule for any needed modifications to equipment and associated procedures necessary for the specified SBO duration.
The NRC has issued Regulatory Guide 1.155 " Station Blackout" which describes a means acceptable to the NRC Staff for meeting the requirements of 10 C.F.R. 50.63.
Regulatory Guide (RG) 1.155 states that the NRC Staff has determined that NUMARC 87-00
" Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout At Light Water Reactors" also provides guidance that is in large part identical to the RG 1.155 guidance and is acceptable to the NRC Staff for meeting these requirements.
Table 1 to RG 1.155 provides a cross-reference between RG 1.155 and NUMARC 87-00 and notes where the RG takes precedence.
Page 1 of 6
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1 ATTACHMENT 1 TO NLR-N89077 l
Public Service Electric & Gas Company (PSE&G) has evaluated the l
Hope Creek Generating Station against the requirements of the SBO I
rule using guidance from NUMARC 87-00 except where RG 1.155 takes precedence.
The results of this evaluation are detailed below.
(Applicable NUMARC 87-00 sections are shown in parenthesis.)
l A.
PROPOSED STATION BLACKOUT DURATION NUMARC 87-00, Section 3 was used to determine a proposed SBO duration of four hours.
No modifications were required to attain this proposed coping duration category.
- However, site specific weather data was utilized in the determination of the appropriate SW and ESW categories (Reference NUS-5175, " Estimated Frequency of Loss of Offsite Power Due to Extremely Severe Weather (ESW) and Severe Weather (SW) for Salem and Hope Creek Generating Stations").
The following plant factors were identified in determining the proposed station blackout duration:
1.
AC Power Design Characteristic Group is P1 based on:
a.
Expected frequency of grid-related Loss of Offsite Power Events (LOOPS) does not exceed once per 20 years (Section 3.2.1, Part 1A, p.
3-3);
b.
Estimated frequency of LOOPS due to extremely severe weather places the plant in ESW Group 2 (Section 3.2.1, Part 1B, p.
3-4);
c.
Estimated frequency of LOOPS due to severe weather places the plant in SW Group 2 (Section 3.2.1, Part 1C, p.
3-7);
d.
The offsite power system is in the I1/2 Groap (Section 3.2.1, Part 1D, p.
3-10);
2.
The emergency AC power configuration group is C based on:
(Section 3.2.2, Part 2C,
- p. 3-13)
I a.
There are four emergency AC power supplies (A, B,
i C and D) not credited as alternate AC power l
sources that provide power to two mechanical l
divisions of shutdown equipment (Section 3.2.2, Part 2A, p.
3-15);
l b.
Two emergency AC power supplies (either A and C or B and D) are necessary to operate one mechanical division of safe shutdown equipment following a loss of offsite power (Section 3.2.2, Part 2B, p.
3-15)
Page 2 of 6
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ATTACHMENT 1 TO NLR-N89077 3.
The target EDG reliability for Hope Creek is 0.95.
This target reliability was selected based on having a nuclear unit average EDG reliability for the last 20 demands greater than 0.90 consistent with NUMARC 87-00, i
Section 3.2.4.
Actual EDG reliability to date is 1.0.
i B.
PROCEDURE DESCRIPTION A
Plant procedures have been reviewed and changes necessary to i
meet NUMARC 87-00 will be implemented in the following i
{
areas:
l 1.
Station blackout response per NUMARC 87-00, Section j
4.2.1 (Reference Procedure; OP-AB.ZZ-135(Q), Station i
Blackout).
Revisions will be made to reflect the need l
for opening of the control room and lower control equipment room doors.
A detailed description of the schedule for procedure revisions is provided in.
2.
AC power restoration per NUMARC 87-00, Section 4.2.2 (Reference Procedures; Electric System Restoration Plan / June 1986, and OP-AB.ZZ-135(Q)).
The Electric System Restoration Plan will be revised to establish a clear priority for repair activities and resource allocation to support 500 kV power restoration to Artificial Island.
OP-AB.ZZ-135(Q) will be revised to identify the necessary actions for stabilizing plant conditions upon recovery of AC power and prior to proceeding to cold shutdown.
A detailed description of the schedule for procedure revisions is provided in.
3.
Severe weather per NUMARC 87-00, Section 4.2.3 (Reference Procedure; OP-AB.ZZ-139(Q), Acts of Nature).
This procedure has been reviewed and is determined to be acceptable in its present form.
Hope Creek has not taken credit for plant shutdown prior to the onset of hurricane winds as a means of improving its coping category.
Additionally, PSE&G takes exception to the NUMARC 87-00 recommendation for EDG start and load test in response to the declaration of a hurricane warning. It is our position that this is an unjustifiable challenge to our first line of defense for loss of offsite power events.
Page 3 of 6
ATTACHMENT l'TO NLR-N89077
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l C.
PROPOSED MODIFICATIONS AND SCHEDULE The ability of Hope Creek Generating Station to cope with a station blackout for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in accordance with NUMARC I
87-00, Section 3.2.5 and as determined in Section "A" above was assessed using NUMARC 87-00, Section 7 with the following results:
1.
Condensate Inventory for Decay Heat Removal (Section 7.2.1) It has been determined from Section 7.2.1 of NUMARC 87-00 that 91,000 gallons of water are required i
for decay heat removal and cool down for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
The l
minimum permissible condensate storage tank level per technical specifications provides 135,000 gallons of water, which exceeds the required quantity for coping with a 4-hour station blackout.
4 2.
Class 1E Battery Capacity (Section 7.2.2)
I A battery capacity calculation has been performed pursuant to NUMARC 87-00, Section 7.2.2 to verify that i
the Class 1E batteries have sufficient capacity to meet station blackout loads for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
3.
Compressed Air (Section 7.2.3)
Air-operated valves relied upon to cope with a station blackout for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> have sufficient backup sources independent of the blacked out unit's class 1E power supplies.
During a station blackout event, the Safety Relief Valves (SRV) will be used for plant depressurization.
These valves are accumulator backed with sufficient capacity to operate for the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> station blackout.
4.
Effects of Lose of Ventilation (Section 7.2.4) a.
Dominant Areas of Concern The steady state ambient air temperature has been calculated for the following dominant areas of concern:
AREA TEMPERATURE HPCI Pump Room 151 F RCIC Pump Room 138 F The temperature in the Main Steam Tunnel was not
{
evaluated because there is no equipment required 1
to function during a station blackout; therefore, the Main Steam Tunnel is not a dominant area of i
concern.
Page 4 of 6
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1 ATTACHMENT 1 TO NLR-N89077 b.
Control Room, and Upper and Lower Control Equipment Rocms the assumption in NUMARC 87-00, Section 2.7.1 that the control room and upper and lower control equipment rooms will not exceed 120*F during a station blackout has been assessed.
-The control room and lower control equipment room at Hope Creek Generating Station do not exceed 120 F during a station blackout with the doors open.
The upper control equipment room will not exceed 120*F with the doors closed.
Therefore, these areas are not a dominant area of concern.
Reasonable assurance of the operability of station blackout response equipment in the above dominant areas of concern has been assessed using Appendix F to NUMARC 87-00 and the Topical Report.
No modifications are required to provide reasonable assurance of equipment operability.
Procedure revisions to require opening control room and lower control equipment room doors are addressed under item B.1 of this response.
5.
Containment Isolation (Section 7.2.5)
The plant Jist of containment isolation valves has been reviewed to verify that valves which must be capable of being c3osed or that must be operated (cycled) under station blackout conditions can be positioned (with indication) independent of the preferred and blacked-out unit's Class 1E power supplies, i
Those containment isolation valves not required to operate in response to the event are assumed to be in their normal position at the onset of the event and to have fa$. led to the design basis position upon loss of power.
Position verification for these valves is not required.
1 Modifications to the Inboard MSIV Drain line, Drywell Sump Drain line, and Drywell Equipment Drain line are required in order to ensure that, when appropriate, containment integrity can be established.
6.
Reactor Coolant Inventory (Section 2.5)
The ability to maintain adequate reactor coolant system inventory to ensure that the core is cooled has been assessed for four hours.
A plant specific analysis was used for this assessment.
During a SBO, the HPCI and RCIC systems will take r.uction from the condensate storage tank to provide makeup to the reactor coolant l
system.
The expected rates of reactor coolant 1
J Page 5 of 6 i
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ATTACHMENT 1 TO NLR-N89077 inventory loss under SBO conditions do not result in core uncovery in a SBO of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Therefore, makeup systems in addition to those currently available under SBO conditions are not required to maintain core cooling.
The modifications identified in Part C above will be completed within two years after the notification provided by the Director, Office of Nuclear Reactor' Regulation in accordance with 10 C.F.R. 50.63 (c)(3).
Revisions to procedures identified in Part B above will be completed in accordance with the schedule provided in Attachment.2 to this response.
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ATTNCHMENT'2'TO NLR-N89077-L 3, jp:i r r
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f0P-AP ZZ-il35(Q)
Station Blackout Revisions'to' Procedure.
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l-3 Initial Operator Training -
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-April 11990-i sa Simul'ator Upgrade (If Appropriate)=
October':1990'
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' (Un-numbered)
Electiic:, System October 1989'
. Restoration Plan I
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