ML17054B332

Summary of 841207 Meeting W/Util & S&W in Bethesda,Md Re Bypass Leakage.List of Attendees & Handouts Encl

ML17054B332
Person / Time
Site:	Nine Mile Point
Issue date:	01/09/1985
From:	Weinkam E Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8501160407
Download: ML17054B332 (40)

Text

NH OiR )985 Docket No.:

50-410 APPLICANT:

Niagra Mohawk Power Corporation (NMPC)

FACILITY:

Nine Mile Point Nuclear Station, Unit 2 (NMP-2)

SUBJECT'UMMARY OF MEETING TO DISCUSS BYPASS LEAKAGE FOR NMP-2 The meeting was held on December 7, 1984, in Bethesda, Maryland.

A list of persons participating in the meeting is included as Enclosure 1.

NMPC presented various drawings (Enclosure

2) to discuss their use of loop seals in containment leakage analyses.

The staff stated that it will be necessary to verify in the plant specific technical specifications the leakage limits for each individual valve relying on a water seal.

NMPC showed that the water leg pressure is not exceeded by containment pressure during an accident.

The staff stated that NMPC will need to justify why the RWCU discharge to feedline does not automatically isolate on a

LOCA.

Also NMPC will need to discuss in more detail the leakage analysis formula for valve leakage included as Enclosure 3.

NMPC will need to provide the required information in the near future to support SSER issuance.

cc:

M. Haughey DISTRIBUTION

~Becket file I

NSIC NRC PBR LBP2 Reading Local PDR

Attorney, OELD PRC System ASchwencer 850jih0407 850i09 PDR ADDCK 050004i0 PDR Edward J.

Weinkam, III, Project Manager Licensing Branch No.

2 Division of Licensing EWeinkam EH lto LBImJ' EWe kam:dh 01/

/85 J

LBIIt2 DL ASchwencer 01/) /55 0(/ gf/8d

4 4

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4

Nine Mile Point 2

Mr. B.

G. Hooten Executive Director, Nuclear Operations Niagara Mohawk Power Corporation 300 Erie Boulevard West

Syracuse, New York 13202 CC:

Mr. Troy B. Conner, Jr.,

Esq.

Conner 8 Wetterhahn

'Suite 1050 1747 Pennsylvania

Avenue, N.W.

Washington, D.C.

20006 Richard Goldsmith Syracuse University College of Law E. I. White Hall Campus

Syracuse, New York 12223 Ezra I. Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector Nine Mile Point Nuclear Power Station P. 0.

Box 99

Lycoming, New York 13093 Mr. John W. Keib, Esq.

Niagara Mohawk Power Corporation 300 Erie Boulevard West

Syracuse, New York 13202 Jay M. Gutierrez, Esq.

U. S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Norman Rademacher, Licensing Niagara Mohawk Power Corporation 300 Erie Boulevard West

Syracuse, New York 13202

f I

Enclosure 1

NINE MILE POINT 2 - DECEMBER 7, 1984 MEETING ATTENDANCE LIST E. J.

Weinkam J.

B. J.

Read R. H. Pinney D. L. Hill M. K. Allen V. B. Patel M. S. Stocknoff P. Visalli K. L. Holsopple J.

A. Kudrick J.

Lane N. Rodmacher D. Pracht NRC/DL NRC/DS I/AEB SWEC Licensing NMPC Licensing SWEC Power/Nuclear SWEC Nuclear Tech.

SWEC Nuclear Tech.

SWEC Ass't Prov.

Engr.

SWEC Nuclear Tech.

NRC/DS I/CSB NRC/DS I/CSB NMPC NMPC

'0 0

I

Enclosure 2

. LQQP..SEAL iRc I oRc PENETRATION I

H~

HH VAPOR OR ATMOSPHERIC PRESSURE APPLICABLE HI ISOLATION VALVES

0

NINE MILE POINT NUCLEAR STATIONUNIT 2 CONTAINMENTPRESSURE RESPONSE FOLLOWING LOCA 50 U

40 V)

CL LUK 30 M

V) lUK Q.

20 K

10 RWCU WATER SEAL PRESSURE CALCULATED LOCA TRANSIENT EQ PROFILE 1

2 3

4 5

10 15 20 25 30 TIMEAFTER LOCA (DAYS)

2WCS.

MOV110 TO CONDENSER 2WCS.

MOV107 EL HEAT EXCHANGERS INSIDE 2WC5-MOV106 REACTOR BLDG M

5/

EL. 256'-9 16" EL. 252'WCS4 M 2WCS'OV112 TO LWS SYSTEM EL. 245'-3" IRC I

I ORC EL. 232'-2 3/8" I

I I

I I

I I

I I

I I

16.76'3.05'"

PIPE I

6" PIPE I

EL 221'-1 1/2" TO TO PUMP1A PUMP18 SUCTION SUCTION EL. 218'-6" VALVE 2WCS-P1A, 18 2WCS y29A 8 REVERSE LEAKAGEFLOW AFTER 40 HOURS I - PIPING ENCLOSED AS SHOWN REPRESENTS MAXIMUMDEGREE OF CONTAINMENTPOST-ACCIDENT ATMOSPHERE INTRUSION INTO PIPING FIGURE 6.2-79 RWCU ARRANGEMENT FROM ISOLATION VALVESTO WATER SEAL NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

Z 43 I

2DFR'MOV139 3I

~

TO RADIOACTIVE LIQUIDWASTE (LWS) 2DF R" MOV140 EL. 255'-6" I

I M

I I

Z 39 M

2DFR'MOV121 EL 217'-9" I

I I

I IRC ORC 2DFR'MOV120 VENT I

I LINE I

1 I

I I

I I

6ri DRAIN LINE I

EL. 252'-9" INSIDE REACTOR BLDG 10NGALLON TANK P MAX = 14.83 PSIG 1

I EL. 184'-8" MINIMUMWATER EL. 183'-6 9/16"

@87 HRS. 4 1HR.

EL. 179'-4 5/8" 2DFR-TK1 TOTAL 500 GAL MINIMUM WATER VOLUME 2DFR-P1A,B FL. EL. 176'-4 3/8" 3

- PIPING ENCLOSED AS SHOWN REPRESENTS MAXIMUMDEGREE OF CONTAINMENT POST-ACCIDENT ATMOSPHERE INTRUSION INTO PIPING REVERSE LEAKAGEFLOW AT 87 HOURS FIGUR E 6.2-80 DFR ARRANGEMENT FROM ISOLATIONVALVESTO WATER SEAL NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

IRC~~ ORC 2

45 2DER'MOV131 VENT TO PRIMARY CONTAINMENT TO RADIOACTIVE LIQUIDWASTE (LWS) 3 EL. 256'-7 4"

INSIDE REACTOR BLDG I

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I 4" DRAIN

)

I I

f 2" VENT~

I 2DER*MOV130 EL. 243'-3" 2

M I

Hl 2" VENT I

I 2DER'MOV120 2DER" MOV119 EL. 216'-6" I

I I

I I

1 I

DRYWELL EQUIPMENT DRAIN COOLER I

I I

i I

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I I

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I I

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L I

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1 00IG ALLON I

TANK I

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I I

I IL 1

PMAX ~ 16.33 PSIG 2DER-TK1 I

I

~w~~

3 llL 3

EL. 188'-1 i4"~

I I.

EL. 184'-8" = MIN.

WATER LEVEL

@81 HRS.

500 GAL MINIMUM WATER VOLUME 5i EL. 179'-4 8" 2PER.F1 MIN. WATER LEVELQ 2DERP3A,B REVERSE LEAKAGF-FLOW AT 81 HOURS EL 176 3

/16-C I - PIPING ENCLOSED AS SHOWN REPRESENTS MAXIMUMDEGREE OF CONTAINMENTPOST-ACCIDENT ATMOSPHERE INTRUSION INTO PIPING FIGURE 6.2-82 DER ARRANGEMENT FROM ISOLATION VALVESTO WATER SEAL NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

P

NINE MILE POINT NUCLEAR STATION.UNIT2 PEAK CLAD TEMPERATURE FOLLOWING A LIME BREAK 2500 2000 DBA RECIRC SUCTION LINE BREAK WITH DIV. I FAILURE 1500 1000 FEEDWATER LINE BREAK WITH HPCS FAILURE 500 0

0 100 200 300 400 500 TlME AFTER BREAK (SECONDS)

50 NINE MILE POINT NUCLEAR STATIONUNIT 2 WATER LEVEL FOLLOWING A LINE BREAK I-LLl LLI ClD0Kx LLl Cl 0)z Lll O

LLJ lX LLlI-40 30 20 10 BAF 100 200 300 TIME AFTER BREAK (SECONDS) 400

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h

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h

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f

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EL 292'-8 1/2" P

{MAX ORC IRC EL.

FROM 6TH PT.

HEATERS

• MOV

• AOV 21A, 21B 23A, 238 l

l l

4AI B l

I l

I

'V12A, I

12B l

l El EL. 2

{ZE ALLINSTRUMENT8 EQUIPMENT II'8 TO BE PREFIXED WITH "2FWS"

REACTOR VESSEL (2MSS*REV 1)

EL 309'-1 3/16" EL. 292'-8 1/2" ORC I IRC PRR016 (MAXGAP 1.6")

SNUBBER EL 274'-11 1/2" FROM 6TH PT.

HEATERS j *MOV / *AOV 21A> 21B,'3A> 23B I

I z

l 4A,B I

I I

I;*V12A, I i 12B I

I (FIRST HIGH STRESS POINT)

D 267'-3 5/8" EL. 266'-3 3/4" PRP017 (ZERO GAP)

EL. 257'-0 5/8"

,. PRR018 j(ZERO GAP)

VERTICAL SEPARATION 7>l ALLINSTRUMENT& EQUIPMENT¹'s TO BE PREFIXED WITH "2FWS>>

5>>

POSTULATED BREAK POINT

'~ (HORIZONTALDEFLECTION = 6 1/2")

FIGURE FEEDWATER LINES (FWS) TO REACTOR PRESSURE VESSEL NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 FINAL SAFETY ANALYSIS REPORT

NINE MILE POINT NUCLEAR STATIONUNIT 2 IODINE PILA7E-GUY

$'p - PLATE-OUT REDUCTION FACTOR FOR ELEMENTALIODINE gp=EXP-ADVD AcVB WHERE:$p: THE REDUCTION FACTOR DUE TO IODINE PLATE-OUT AD = PIPE DEPOSITION AREA VD = 9.0 X t0 8 EXP 8100 RTs (CM/SEC)

R = BOLTEMAN'S CONSTANT = 1.987 Ts = STEAM TEMPERATURE, 'K Ac = PIPE CROSS SECTION AREA VB =- STEAM FLOW VELOCITY NOTE: Q = AgVB

NINE MILE PGINT NUCLEAR STATIGNUNIT 2 IGDINE PLATE-GUT REDUCTIGN FACTGRS FGR MAIMSYEAM PIPIMG AD = 5 I5ft'

=QT, WHERE QTIS TEST FLGW RATE Ts{'K}

8100 QD 9.O X Io Ej(P RT (oK~

NINE MILE POINT NUCLEAR STATION.UNIT 2 IGDINE PLATE-GUT REDUCTIGN FACTGRS FGR MAINSTEAM PIPING P-MS Ts 'K 307'K (93'F) 414'K (286'F) 561'K (550'F Qq (scfh) 1.0 0.0 0.0 1.73-2 5.5 0.0 1.81-6 4.78-1 10.0 0.0 6.95-4 6.67-1 NOTE: VALUES LESS THAN 10 "ARE QUOTED AS 0.0 CHI~ ill~

NINE MILE POINT NUCLEAR STATIONUNIT2 IGI3INE PI ATE-GUT REDUCTIGN FACTGRS FGR FEEDWAYER PIPING AD = 259 ft2 Ts('K)

Q

=Qq 288'K VD = 9.0 X 10-8 exp 8 IOO RTs('K)

NINE MILE POINT NUCLEAR STATIONUNIT 2 IGI3IME PLATE-GUY REDUCTIGM FACYGPS FGR FEEDWATER PIPIMG P-FW Ts 'K Q~

307'K (93'F) 414'K (286'F) 561'K (550'F)

(scfh}

1.0 0.0 0.0 1.31-1 0.0 1.31-3 6.91-1 10.0 0.0 2.60-2 8.16-1 NOTE: VALUES LESS THAN 10 "'RE QUOTED AS 0.0

NINE MILE POINT NUCLEAR STATIONUNIT 2 OVERALLPLATE-GUT REDUCTIIOIM FACTORS

,Q9 F = $p (.91) + 1.0(0)*

• REGULATORYGUIDE 1.3 STATES THAT ONLY 91% OF THE IODINE RELEASED IN A LOCA IS ELEMENTAL Ts ('F)

MAINSTEAM 5.5scfh 286 550 FMs 0.09 0.09 0.52 Ts('F)

FEEDWATER @5.5scfh 286 550 FFw 0.09 0.09 0.72

Enc1osure 3

EaY xkzF= MA'.aN.xkAK)mK~c~

W-. 3..Z.cMP s FFmxe~hmQ]XL.~PE m 5X LLs3s

.MDq MKPQLZ..JRlK~LANS.LfTLNJE. OIllMrl l K.OLAT1QR VALVE5 Q. CKED1WMM. QDlAMQRK~.Vbl VP3.

RPZVR IC.T> Nb t=

QT Z9z

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