ML17251A453
| ML17251A453 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/17/1989 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8904270352 | |
| Download: ML17251A453 (8) | |
Text
AQCEl+RATED DiOKBUTJON DEMO%STTIOA'YSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
SUBJECT:
Submits info re station blackout,per 10CFR50.63.
DISTRIBUTION CODE:
A050D COPIES RECEIVED:LTR i ENCL SIZE:
TXTLE: OR Submittal: Station Blackout (USI A-44) 10CFR 0.63, MPA A-2 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
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05000244 S
ACCESSXON NBR:8904270352 DOC.DATE: 89/04/17 NOTARIZED:
NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFXLIATION MURLEY,T.E.
Office of Nuclear Reactor Regulation, Director (Post 870411 R
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ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649 0001 April 17, 1989 TELEPHONK Awe*coos v>e 546-2700 Thomas E. Murley, Director Office of Nuclear Reactor Regulation, United States Nuclear Regulatory Commission 1 White Flint North Rockville Pike Rockville, Maryland e
Subject:
10 CFR 50.63 Station Blackout R.E.
Ginna Nuclear Power Plant Docket Number 50-244
Dear Mr. Murley:
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 added, which requires that 'each light-water-cooled nuclear power plant be able to withstand and recover from a station blackout of a specified duration.
Utilities are expected. to have the baseline assumptions, 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 station blackout duration, the plant be capable of maintaining core cooling and. appropriate containment integrity.
Section 50.63 further requires that each licensee submit the following information:
l.
A proposed station blackout duration including a justification for the selection based.
on the redundancy and reliability of the onsite emergency AC power
- 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 recovery therefrom; and 3.
, A list and proposed schedule for any needed'modifications to equipm'ent and associated procedures necessary for the specified "station blackout duration.
S904270352 8904i7 PDR ADOCK 05000244 P
T
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 CFR 50.63.
Regulatory Guide 1.155 states that the NRC Staff has determined that Nuclear Management And Resources Council (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 Regulatory Guide 1.155 guidance and is acceptable to the NRC Staff for meeting these requirements.
Table 1 to Regulatory Guide 1.155 provides a cross-reference between Regulatory Guide 1.155 and NUMARC 87-00 and notes where Regulatory Guide 1.155 takes precedence.
Rochester Gas And Electric Corporation has evaluated the R.E.
Ginna Nuclear Power Plant against the requirements of the station blackout rule using guidance from NUMARC 87-00 except where Regulatory, Guide 1.155 takes precedence, and except for the analyses for effects of loss of ventilation, where a plant-specific analysis was'sed.
The results of this evaluation are detailed below.
Applicable NUMARC 87-00 sections are shown in
'arenthesis.
A.
Pro osed Station Blackout Duration NUMARC 87-00, Section 3 was used. to determine a proposed station blackout duration of four hours.
No modifications to station equipment or procedures were required to attain this proposed coping duration category.
The following plant factors were identified in determining the proposed station blackout duration:
1.
The AC Power Design Characteristic Group is P2 based on the following:
a ~
The expected frequency of grid-related losses of offsite power (LOOPs) does not exceed once per 20 years (Section 3.2.1, Part 1A, p. 3-3);
b.
The estimated frequency of LOOPs due to extremely severe weather places the plant in ESW Group 1
(Section 3.2.1, Part lB, p. 3-4);
c ~
d.
The estimated frequency of LOOPs due to severe weather places the plant in SW Group 3 (Section 3.2.1, Part lC, p. 3-7); and, The offsite power system is in the I1/2 Group (Section 3.2.1, Part lD, p. 3-10);
2.
The emergency AC power configuration group is C
(Section 3.2.2, Part 2C, p. 3-13) based on the following a.
There are two emergency AC power supplies not credited as alternate AC power sources (Section 3.2.2, Part 2A, p. 3-15); and, b.
One emergency AC power supply is necessary to operate safe shutdown equipment following a loss of offsite power (Section 3.2.2, Part 2B, p. 3-15).
3.
The target EDG reliability is 0.975.
a ~
A target EDG reliability of 0.975 was selected based on having a nuclear unit average EDG reliability for the last 100 demands greater than 0.95, consistent with NUMARC 87-00, Section 3.2.4.
B.
Procedure Descri tion Plant procedures have been reviewed in the following areas, as per the guidelines in NUMARC 87-00, Section 4:
Rochester Gas And Electric Power Control Department Emergency Procedures A, "Restoration Of The RG&E Bulk Transmission System By Way Of Stations 80 And 122 From The 345 KV System,"
B, " Restoration Of The RG&E Generation System Utilizing Station 5 Hydro," C, "Restoring The RG&E. Generation And. Transmission System By The Use Of The Peaking Turbines At Station 3," and D, "Restoration Of The RG&E System Using The Gas Turbine At Station 9," were reviewed with respect to AC power restoration per NUMARC 87-00, Section 4.2.2;
- and, 2.
SC-2, Revision 15, "Adverse Weather Emergency Plan,"
was reviewed with respect to station blackout due to severe weather per NUMARC 87-00, Section 4.2.3.
Other plant procedures were also reviewed per NUMARC 87-00 in the following areas:
ECA-O.O, Revision 6, "Loss Of All AC Power," ECA-0.1, Revision 2, "Loss Of All AC Power Recovery Without SI Required,"
ECA-0.2, Revision 3, "Loss Of All AC Power Recovery With SI Required,"
and ER-AFW.1, Revision 3, "Alternate Water Supply To The AFW Pumps,"
were reviewed with respect to station blackout response per NUMARC 87-00, Section 4.2.1.
C.
Pro osed Modifications and Schedule The ability of the R.E. Ginna Nuclear Power Plant to cope with a station blackout for four hours in accordance with NUMARC 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:
Condensate Inventor For Deca Heat Removal (Section 7.2.1)
It has been determined from Section 7.2.1 of NUMARC 87-00 that 50,000 gallons of water are required for decay heat removal for four hours and plant cooldown.
The minimum permissible condensate storage tank level per current technical specifications provides 22,500 gallons of water.
The following additional water sources have been identified as being available to provide the total required amount of condensate:
a.
The 110,000 gallon outside storage tank as per procedure ER-AFW.1, step 4.2.2; b.
City water as per procedure ER-AFW.1, step 4.6;
- and, c.
The plant fire water system as per procedure ER-AFW.1, step 4.7.
No plant modifications or procedure changes are needed to utilize these water sources.
2.
Class lE Batteries Ca acit (Section 7.2.2)
A battery capacity calculation has been performed pursuant to NUMARC 87-00, Section 7.2.2 to verify that the Class lE batteries have sufficient capacity to meet station blackout loads for four hours.
For operational convenience, RGGE plans to investigate the possibility of adding additional instrumentation to battery-backed buses.
Com ressed Air (Section 7.2.3)
Air-operated valves relied upon to cope with a station
-blackout for four hours can either be operated manually or have sufficient backup sources independent of the preferred and blacked out Class lE power supply.
Valves requiring manual operation or that need backup sources for operation are identified in plant procedures.
4.
Effects of Loss of Ventilation (Section 7.2.4)
The calculated steady state ambient air temperature for the intermediate building containing the steam driven AFW pump (the dominant area of concern for a PWR) during a station blackout induced loss of ventilation is 145 'F.
The assumption in NUMARC 87-00, Section 2.7.1 that the control room will not exceed 120 'F during a station blackout has been assessed.
There is reasonable assurance that the control room at the R.E.
Ginna Nuclear Power Plant will not exceed 120 F during a station blackout.
Therefore, the control room is 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/or the Topical Report.
No modifications or associated procedures are required to provide reasonable assurance for equipment operability.,
5.
Containment Isolation (Section 7.2.5)
The plant list of containment isolation valves has been reviewed to verify that valves which must be capable of being closed or that must be operated (cycled) under station blackout conditions can be positioned (with indication) independent of the preferred and blacked-out Class lE power supplies.
No plant modifications and/or associated procedure changes were determined to be required to ensure that appropriate containment integrity can be provided under station blackout conditions.
6.
Reactor Coolant Inventor (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.
The generic analyses listed in Section 2.5.2 of NUMARC 87-00 were used for this assessment and are applicable to the specific design of the R.E. Ginna Nuclear Power Plant.
The expected rates of reactor coolant inventory loss under station blackout conditions do not result in uncovering the core in a station blackout of four hours.
Therefore, makeup systems in addition to those currently available under station blackout conditions are not required to maintain core cooling under natural circulation (including reflux boiling).
The modifications and associated.
procedure changes identified in Parts A, B, and C above will be completed within two years of the notification provided. by the Director., Office of Nuclear Reactor Regulation in accordance with 10 C.F.R. 50.63(c)(3).
Very truly yours, Robert C.
Me dy, General Manager Nuclear Production RCMN031