ML19325C654
| ML19325C654 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/10/1989 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-REGGD-01.155, RTR-REGGD-1.155 NLS-89-256, TAC-68520, TAC-68521, NUDOCS 8910170144 | |
| Download: ML19325C654 (10) | |
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}7 CaroEne Pouver & Light Conipeny e,
k P.O Box 1651
- Raiogh. 4C. 27e02
- OCT 1 01989 -
j SERIAL: NLS 89-256=
10 CFR 50.63 h4
' A. B CUTTER ;
P
... f Vice Proeident
. NuCmr Services Department u
e$,
' United States Nuclear' Regulatory Commission R'
ATTENTION: Document Control Desk
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Washington, DC 20555 Im BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS 1~AND 2 DOCKET NOS.- 50425 & 50 324/ LICENSE NOS. DPR 71 & DPR-62.
REVISED RESPONSErTO STATION'BIACKOUT RULE (NRC TAC NOS.-68520 AND 68521) l
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Gentlemen:-
1 "On March 3, :1989, Carolina Power.& Light Company responded to the Station y"
~ Blackout: Rule,-_10.CFR 50.63, for the 3runswick Plant. This response nidentified the Brunswick Plant as' meeting the coping requirements as'an_AC' independent 1 station. Representatives-from the'NRC Staff conducted a review s
9t-the'back' ground documents which supported the rule respor.se during a~
~
-visit?to our facilities from June 27 to June 30', 1989. As a result of this~
1
- review and our-_ analysis of additional information~obtained-during these
'j discussions, the Brunswick Plant.is reclassifying the coping approach as'
- alternatt AC.
The purpose of this letter is: to revise: our previous response to the Station Blackout Rule l(SBO) to reflect this change. The
.i
__following replaces our response of March'3, 1989.
The change bars in'the
_ margin identify ~the information revised from the March 3; 1989 response.
Carolina Power & Light Company has evaluated ~the Brunswick Steam-Electric j
. Plant', Units l'and 2 against:the requirements of the Sao rulo using
, guidance from NUMARC'87-00 except where RG 1.155 takes precedence. The ti i,
resultsLof this evaluation are-detailed below.
(Applicable NUMARC 87-00 sectionsLare e,hown in parenthesis.)'
.A.
_Prooosed Station Blackout Duration m4 L
NUMALC.87-00, Section 3 was used to determine a proposed SB0 duration of four hours. No modifications were required to attain this proposed coping' duration category.
l The'following-plant factors were identified in determining the proposed l
-station blackout duration:
- l..AC Power Design Characteristic Group is P3*-based on:
.a. -Expected frequency of grid related LOOPS - does not exceed once per-20 years (Section 3.2.1, Part lA, page 3-3);
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. NLS 89 256;/,Page 1 '" g..
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Estimated frequency ot LOOPS due to extremely severe weather 9"
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-places the plant in ESW. Croup 5-(Section 3.2.1, Part IB, page 3-4);
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Estimated frequency of-LOOPS due to severe weather places the-
~ lant in SW Croup 2 (Section 3.2.1, Part IC, page 3-7);
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The off-site power system is in the 13. Group (Section 3.2.1,-
p' i,ro Part ID, par 310);
'e.
Plant-specific pre-hurricane shutdown requirements and
' procedures which meet the guidelines of Section 4.2.3 of NUMARC'87 00 have been implemented.
I'-
2.
.The emergency AC power configuration is C based on: s.iect_on 3.2.2, Part 20,.page 3 13) a.
.There are two emergency AC power supplies not credited as alternate AC power sources per unit (Section 3.2.2, Part 2A.
.page 3-15) b..-One emergency AC power supply per-unit is necessary to operate safe shutdown equipment following'a loss of off-site power (Section 3.2.2, Part 2B, page 3-15) a i
a
'3.
'The-target EDC reliability.is 0.975.
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~A-target EDC reliability of 0.975,was selected based on having r
-nuclear unit average EDC reliability for the last 100 demands greater than 0.95 consistent ~with NUMARC 87-00, Section 3.2;4.
1
-4.
An alternate:AC (AAC) power source will be utilized.at the t
. Brunswick Plant which meets the criteria specified in Appendix B to NUMARC 87-00.
The AAC source is remerve capacity from the adjacent q
unit's EAC power source which meets the assumptions in Section 2.3.1 of NUMARC 87-00.
The reserve capacity.will be made-
{
available to the blacked out unit through an existing cross tie between the Unit 1 and Unit 2 4160 VAC buses. Modifications which enhar.ce the. cross: tie feature are described in'Part C of this
~1etter. -The attached figures show-the cross tie arrangement that
~
provides the AAC capability.
A separate figure for each single EAC i
-power source is provided, i
3, :.
-The AAC powerfsource is available within one hour of the onset of the' station blackout event and has sufficient capacity and j
capability.ro operate systems necessary for coping with a station blackout forithe required SB0 duration of four haurs to bring and
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maintain the plant in safe shutdown. An AC independent coping analysis was performed for the one hour required to bring the AAC power source on line, i
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NLS 89-256 // Page 3 I'
N B.
-Procedure Deggrintion j
b Plant procedures'have been reviewed and modified, if necessary, to meet
~
the guidelines in NUMARC 87-00, Section 4 in the following areas:
1 1.
AC power restoration'per NUMARC 87-00, Saction 4.7.2:
o Procedure DTRM CP-2; Restoration of Service Following a System
. Shutdown - Eastern Area; a~
o Operating Procedure OP 50; Plant Electrical System Operating i
Procedure;
.)
o Operating Procedut 1P 50.1; Diesel Generator Emergency Power
.I System Operating Procedure.
o 2.
Severe weather per NUMARC 87-00, Section 4.2.3:
o BSEP Administrrtive Instruction AI-68; Brunswick Nuclear Project Response to Severe Weather. Warnings;
-f Abnormal Operating Procedure AOP 13.0; Operation During o
~
Hurricane, Tornado or Flood Conditions.
Plant'proceduresLhave=been reviewed and changes necessary to meet NUMARC 87 00 will be implemented in the following areas:
1.
Station blackout response per NUMARC 87 00, Section 4.2.1; e
o Emergency Operating Procedures, BSEP E0P-01 o,
Abnormal Operating Procedure, AOP 36.0; Loss of Off-site Power
? 2. - Procedure changes arsociated with any modifications required after assessing coping capability per NJMARC 87-00, Section 7.
s C; ;Pronosed Modifications and Schedule g
.fgiifications To Use AAC Power Source 3.1 The existing cross. tie breakers between the unit 4160 VAC buses are l
L currently maintained in the racked oue position to minimize the potential for inadvertent cross connection of the emergency buses. The existing control circuits for the cross tie breakers are provided with
'<p inter?.ocks and permissives to rostrict certain breaker alignments during normal operation..During conditions or' a postulated station blackout, several of these breaker interlocks and permissives must be overridden to employ the AAC source.
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The modification will isolate the LOCA interlocks and permissives that f".
might inhibit operation of the breakers during station blackout conditions.
During normal operation, control power to the breakers will be de-energized by installing a local key locked switch positioned 1
to remove control powar.
This will permit the breakers to be m
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maintained in.the racked in position durir: normal operation with no
. potential for spurious operation due to an electrical fault-or control
-room fire.
Inadvertent operation of the breakers will be prevented by controlling access to'the keys for the key-locked switch..The cubicles will be conspicuously labeled such that no switches are to be operated to energize breaker control circuits except dud.rg an emergency such as a station blackout.
During such-an emergency, '.ne key-locked switch l
.will be repositioned to energize the control poser circuit.to allow operation of the breakers.
[
The equipment required for a SB0 that will be affected by. the
' modifications are the emergency switchgear buses for~both units:
El and E2 in 11 nit'1, E3 and' E4 in Unit 2.
The specific switchgear
' cubicles L(breakers) affecced by the modificat?.ons are identified below:
}
Egg Cubiele' Descrintion El AGO Tie Breuker El to E3 E2 AH9 Tie Breaker E2 to E4 E3 AJS Tie Breaker E3 to El E4 ALS Tie Breaker E41to E2 i
As part of the modification, unit specific performance testing will be accouplished to ensure proper operation of each respective unit's breakers subsequent to the modifications.
The AAC source'has the capacity and' capability to power the equipment necessary to cope with a SB0 in accordance with NUMARC 87 00, Section.7
~
for the required coping duration determined in accordance with NUMARC 87-00, Section 3.2.5.
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 100,380 gallons of water are required for decay heat removal for
.l the four hour coping duration-category from'NUMARC 87-00, Section 3.2.5. 'The minimum required condensate storage tank-level is met through compliance with the existing plant procedure 01-3.6 which requires the condensate storage tank to be maintained'at a level greater than 10 feet; this level provides a usable volume of 103,738 gallons of water, which exceeds the required quantity for
. coping with a four-hour station blackout. The tank is normally maintaited at a level in excess of 20 feet (approximately 250,000 gallons) 01-3.6 requires hourly readings and reports if the tank level dro,7s below 15 feet (app.vximately 180,000 gallons).
2.' Class 1E Battery Canacity (Section 7.2.2)
A battery capacity calculation has verified that the Class 1E battery has sufficient capacity to meet station blackout loads for one hour, at which time a battery charger will be powered from the AAC power source.
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g;aoressed' Af r - (Section 7. 2.4)
Air operated,' valves-that are relied upon to cope with a station Eblackout for four hours have-sufficient backup sources independent
- of the preferred and blacked out unit's Class E power supply
-l l
4.
Effects of Loss of Ventilation (Section 7.2.4)
~
a.
The steady'atate. ambient air temperature has been calculated 3
d for the fellowing dominant areas of concern:
7 AIRA 7emoarature HPCI 152 F RCIC Room and Pipe Chase 145 F ECCS Pipe Tunntl 131 F b.- The-assumptions in NUMARC 87-00, Section 2.7.1 thst the control' room will not exceed 120 F during a station blackout have been assessed. The control room at eSEP, Units 1 and 2 will not exceed 120 F.during a station bleckout.
Therefore, the control room is not a dominant area of concern.
NUMAEC 87-00 requires operator action to open cabinet doors for
+:
coping equipment in'the control room complex within 30 minutes i
of SB0Linduced loss of ventilation.
Control room HVAC will be i
available.immediately if the AAC source is either EDC 1, 3, or 4.
.Only;in the instance chat EDC 2 is the AAC power source will control room ventilation be unavailab'..e until the crose connect is completed.
Therefore, rather than divert operators to opening-cabinet doors, efforts'will be directed toward establishing;the cross connection of the emergency buses to use EDC 2 'and re atore ventilation.
Should ditficulties arise in establishing the cross connection, opening of the cabinet doors i
for coping equipment in the control room complex will begin, r
Reasonable assurance of the opertullity 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 Repcrt. No modifications or associated procedures are n
required to provids reasonable assurance for eouipment operability.
b 5.
Containment (Section 7.2.5)
I The plant list of containment isolation valves has been reviewed to verify that "alves wbica must be capable of being closed or that must be operated (cyclad) under station blackout conditions can be positioned (with indication) independent of the preferred and blacked out unit's Class 1E power supplies.
The following procedure changes are required to ensure that eppropriate l;
containment integrity can be provided under station blachout conditions:
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fNLS-89-236 f Page-6' Ic i f;'
Abnormal Operating Procedure AOP-36~.0 will be revised to
/'
isequentially supply power from the AAC power source to MCCs XA.,XB, 1XC, and XD in the blacked out unit to monitor position and/or close z
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_a select grouping ofLRHR and core spray valves.
~
- 6..Seactor Coolant Inventory (Section 2.5)
The ability-to maintain adequate reactor coolant system inventory to ensure that the cora 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 essassment and are applicable to the specific design of BSEP. The expected rates of reactor coolant' inventory lo.s under SBO conditions do not result in more than a momentary core uncovery in:a'.SB0 of four hours., Therefore, make-up sfrstems.in
' addition to those currently available under SB0 condit11ns are not
~
required to maintain core cooling under 'atural circulation n
(including reflux boiling).
In addition to the modifications associated with establishing an AAC power source, an AC. independent containment pressare indication will be provided.
'Further analysis ~ indicates that the previously identified modification-for enhanced battery voltage indication will not be required.
The modifications and associated' procedure changes identified in parts B.
and C above will:be cotopleted within two years after the notification provided;by 'che Director, Office of Nuclear Reactor Regulation in
'accordance'with 10 CFR 50,63(c)(3)..
Ii1 you shocid have any questions, please contact Mr. S. D. Floyd at
.(919) 546-6901.
Yours very truly, f
A..B.
Cutter ABC/sdf:
Enclosure cc:
Mr. S. D. Ebneter Mr. W. H. Ruland 1
Mr. E. G. Tourigny NUMARC
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