ML17321A455

Summary of 850206 Meeting W/Util & Bmi Re Program for Resolution of Hydrogen Control Issues.List of Attendees, Meeting Objectives & Hydrogen Control Program Objectives Encl

ML17321A455
Person / Time
Site:	Cook
Issue date:	02/14/1985
From:	Wigginton D Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8502250926
Download: ML17321A455 (26)

Text

February 14, 1985 Docket Nos.'0-315

',and 50-316 LICENSEE: Indiana and Michigan Electric Company (IMEC)

FACILITY: Donald C.

Cook Nucleap Station, Unit Nos.

1 and 2

SUMMARY

OF MEETING HELD ON FEBRUARY 6, 1985 WITH IMEC TO DISCUSS HYDROGEN CONTROL FINAL RESOLUTION The staff met with the licensee, IMEC, and their representatives from Battelle Columbus to discuss the Donald C.

Cook Nulcear Station program for final resolution of the hydrogen control issue.

The Cook plants have ice-condenser containments and the new rule, 10 CFR 50.44, noticed in the Federal Register on January 25, 1985 applies directly to Cook.

The list of attendees is attached as Enclosure I.

The IMEC has decided to undertake a new and complete approach to resolution of the hydrogen control issue for Cook.

Some previously developed information may be referenced but for the most part, a complete and definitive set of documented information will be submitted to the NRC to support a safety evaluation..

The proposed schedule and other details of the program are included in the viewgraphs attached as Enclosure II.

From the discussions it was determined that the structural integrity issue has been resolved as long as the IMEC has adopted the 36 PSIG criteria for internal pressure.

For anything greater, IMEC is encouraged to discuss the issue with the staff at the earliest convenience.

The MARCH code will be used for the hydrogen/steam source term.

NRC review will be required along with input decks to assure applicability to the D.

C.

Cook containment and systems.

This review may take some time and IMEC was requested to submit this information early in the review.

IMEC will also propose a burn model and input parameter early in the review for NRC review.

The selection of accident sequences is to be made before the study; NRC concurrence on the selection ear ly in the program was suggested to avoid delays later.

The schedule presented by the IMEC is to be revised in light of the above discussions and the time required for NRC review early in the process.

The licensee will revise the schedule and submit it and other information to the NRC upon initiation of the program.

/s/DLWigginton David L. Wigginton, Project Manager Operating Reactors Branch ¹1 Division of Licensing ORB¹ DLWi ginton/ts 02/7 /85 850225092b 850214 PDR ADOCK 050003l5 P

PDR

I

'Al PA

~

I "A) lt II' A ~

'AIIA I

II h

I 4 4

A

'l t I'

I H

hh F

4 A

I' AP F

A I

Il

MEETING

SUMMARY

DISTRIBUTION Docket or:Central file NRC PDR Local PDR ORBgl RDG J. Partlow (Emergency Preparedness only)

Steve Varga Project Manager OELD E. Jordan P.

McKee ACRS (10)

NSIC Gray file Plant Service List C. Parrish J. Partlow NRC Partici ants

/p lI II l Lg t

11 r

f~'

gpss REoy

+0 Po Op C

O I

C Ol O~

gO

~ +a**+

Docket Nos.

50-315 and 50-316 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 February 14, 1985 LICENSEE: Indiana and Michigan Electric Company (IMEC)

FACILITY: Donald C.

Cook Nuclear Station, Unit Nos.

1 and 2

SUMMARY

OF MEETING HELD ON FEBRUARY 6, 1985 WITH IMEC TO DISCUSS HYDROGEN CONTROL FINAL RESOLUTION The staff met with the licensee, IMEC, and their representatives from Battelle Columbus to discuss the Donald C.

Cook Nulcear Station program for final resolution of the hydrogen control issue.

The Cook plants have ice-condenser containments and the new rule, 10 CFR 50.44, noticed in the Federal Register on January 25, 1985 applies directly to Cook.

The list of attendees is attached as Enclosure I.

The IMEC has decided to undertake a

new and complete approach to resolution of the hydrogen control issue for Cook.

Some previously developed information may be referenced but for the most part, a complete and definitive set of documented information will be submitted to the NRC to support a safety evaluation..

The proposed schedule and other details of the program are included in the viewgraphs attached as Enclosure II.

From the discussions it was determined that the structural integrity issue has been resolved as long as the IMEC has adopted the 36 PSIG criteria for internal pressure.

For anything greater, IMEC is encouraged to discuss the issue with the staff at the earliest convenience.

The MARCH code will be used for the hydrogen/steam source term.

NRC review will be required along with input decks to assure applicability to the D.

C.

Cook containment and systems.

This review may take some time and IMEC was requested to submit this information early in the review.

IMEC will also propose a burn model and input parameter early in the review for NRC review.

The selection of accident sequences is to be made before the study; NRC concurrence on the selection early in the program was suggested to avoid delays later.

The schedule presented by the IMEC is to be revised in l,ight of the above discussions and the time required for. NRC review early in the process.

The licensee will revise the schedule and submit it and other information to the NRC upon initiation of the program.

David L.

Wi ton, Project Manager Operating Reactors Branch Pl Division of Licensing

Enclosure I

HYDROGEN CONTROL MEETING WITH DONALD C.

COOK -

FEBRUARY 6, 1985 D. Wigginton H. Garg R. Palla, Jr.

K. Parczewski D. Medek J. Feinstein M. Leonard G. Lear P.

Kuo M. Alexich R. DiSalvo P. Cybulskis T. Crawford H.

Fouad C.

Tan Or anization NRR-ORB-I NRR/DE/EgB NRR/DS I/CSB NRR/DE/CMEB AEPSC/NOD/NSL AEPSC/NOD/NSL Battelle Columbus TSGEB/NRR/NRC NRR/DE/SGEB AEPSC/NOD Battelle Columbus Battelle Columbus AEP/NS8L AEP/NOD/NSl NRR/DE/SGER

Enclosure II 6

8 OBJECTIVES OF THE MEETING:

DISCUSS THE D. C.

COOK NUCLEAR PLANT HYDROGEN CONTROL PROGRAM WITH NRC STAFF.

DISCUSS THE SCOPE OF WORK WHICH AEPSC PROPOSES TO HAVE BATTELLE COLUMBUS LABORATORIES PERFORM RELATIVE TO THE D. C.

COOK NUCLEAR PLANT PROGRAM.

DISCUSS THE PROPOSED SCHEDULE FOR PROGRAM COMPLETION, AND OBTAIN NRC STAFF CONCURRENCE. WITH THE SCHEDULE.

ASCERTAIN WHETHER COMPLETION OF THE PROPOSED PROGRAM WILL ENSURE COMPLIANCE WITH THE RECENT HYDROGEN CONTROL RULEMAKING, 10 CFR go.44(C).

ANALYZE THE D. C.

COOK NUCLEAR PLANT ICE CONDENSER CONTAINMENT FOR,

RESPONSE

TO HYDROGEN BURN SCENARIOS OTHER THAN THE SMALL BREAK LOSS-OF-COOLANT ACCIDENT (LOCA).

SCENARIOS INCLUDE A HIGH REACTOR COOLANT SYSTEM (RCS)

PRESSURE

SCENARIO, AN INTERMEDIATE RCS PRESSURE

SCENARIO, AND A LOW RCS PRESURE SCENARIO, IN ORDER TO VARY HYDROGEN RELEASE RATES TO CONTAINMENT.

IN-VESSEL HYDROGEN GENERATION RATES WILL BE ANALYZED WITH MARCH 2;

CONTAINMENT RESPONSE WILL BE ANALYZED WITH CLASZX.

DEFINE THE EFFECT OF THE AIR RETURN/HYDROGEN SKIMMER SYSTEM FANS AND THE RCS VENT SYSTEM DISCHARGE POINTS ON CONTAINMENT HYDROGEN DISTRIBUTION.

DEFINE THE EFFECT OF THE CONTAINMENT SPRAYS AND ATMOSPHERIC CROSS-PLOW VELOCITIES ON THE EFFECTIVENESS OF THE GLOW PLUG IGNITERS.

DETERMINE IF THE RANGE OF SCENARIOS INDICATES A POTENTIAL FOR LOCAL DETONATION OF HYDROGEN.

ZF SO, GENERATE A CONTAINMENT DYNAMIC LOADING FUNCTION AND PERFORM A CONTAINMENT DYNAMIC STRUCTURAL ANALYSIS.

DEFINE THOSE EQUIPMENT ITEMS WHICH ARE REQUIRED TO FUNCTION DURING AND AFTER A POSTULATED HYDROGEN BURN EVENT.

R M

WEEKS AFTER START Review Proposed Program Approach With NRC Staff Review MARCH 2 Analysis Input With AEPSC Staff Perform Initial Set of MARCH 2 Analyses For In-Vessel Hydrogen Generation Define Effect Of Reactor Coolant System Vent Routing Define Effect Of Air Return/Hydrogen Skimmer System Fan Operability AEPSC And BCL Complete And Verify Input Decks For CLASIX Analyses (Three Acoident Scenarios) e 9

9, 11, 13 Assess Effects Of Spray Impingement And Related Factors On Glow Plug Igniter Effectiveness Interim Program Review With NRC Staff Determine If Possibility Of Local Detonations Exists; Zf So, Develop Detonation Loads For Dynamio Containment Analysis Draft Report Issued By BCL AEPSC Review Of Draft Report Final Report Issued By BCL NRC Notified Of Final Resolutions Of BCL Work And Containment Dynamio Analysis 15 16 23 26 36 40 44

SEVERE ACCIDENT ANALYSIS PLAN A BASIS FOR RESOLVIHG I SSUES CONCERNING HYDROGEN COMBUSTION AND CONTROL AT D C

COOK MARK T LEONARD BATTELLE COLUMBUS LABORATORIES AEP

".','Bamelle Columbus Laboratories

PROGRN PLAN SCOPE

~

CALCULATE THE RANGE OF PHYSICALLY REALISTIC HYDROGEN SOURCE TERMS FOR SEVERAL REPRESENTATIVE ACCIDENT SCENARIOS

~

DETERMINE THE TIME DEPENDENT DISTRIBUTION OF H2 AND PRESSURE TEMPERATURE LOADS IN CONTAINMENT POSSIBLE RECIRCULATION FAN FAILURE ROUTING OF HIGH POINT VENT LINE

~

EXAMINE THE POSSIBILITY OF DEVELOPING GAS COMPOSITIONS THAT REQUIRE CONSIDERATION OF LOCAL DETONATIONS

~

IF DETONABLE COMPOSITIONS ARE PREDICTED'EFINE THE TRANSIENT PRESSURE HISTORIES (FORCING FUNCTION)

FOR CONTAINMENT STRUCTURE DYNAMIC ANALYSIS 0

DETERMINE THE POTENTIAL FOR REDUCED IGNITER EFFECTIVENESS DUE TO SPRAY IMPINGEMENT OR GAS VELOCITIES AEP

'.".".'Battelle Columbus Laboratories

ANALYTICALTOOLS

~

HYDROGEN/STEAM SOURCE TERMS

~

CONTAINMENT RESPONSEl

~

BETONATION PRESSURE RESPONSEl MARCH 2 CLASIX CHAPMAN JOUGUET THEORY AEP

".'.'.Batfelle Columbus Laboratones

APPROACH FOR DEVELOPING H /H 0 SOURCE TERMS

~

SELECT SET OF ACCIDENT SCENARIOS THAT COVER REPRESENTATIVE RANGE OF GAS RELEASE RATES TO THE CONTAINMENT LOW PRIMARY SYSTEM PRESSURE INTERMEDIATE PRIMARY SYSTEM PRESSURE

= S20 HIGH PRIMARY SYSTEM PRESSURE

= TMLU' TIME OF RESTORED COOLANT INJECTION WILL BE TREATED PARAMETRI CALLY TO ALLOW SEVENTY FIVE PERCENT ZIRCONIUM OXIDATION

~

ONLY CORE DEGRADATION SCENARIOS WILL BE CONSIDERED (RESTORATION OF ECC IS ASSUMED TO ARREST 2R OXIDATION AND PREVENT CORE MELTDOWN)

AEP

".:".",.'.Baffelle Columbus Laboratones

y LB/MIN PWR TMLU FOR ILLUSTRATION ONLY NOT A DeCe COOK ANALYSIS P4 O

P4 id 10 10 1d 10 Event Steam Gen.

Dry Core Uncover Start Melt Start ECC Time, min 75 174 192 210 I

p I

HYDROGEN t

I t

I I

I I

r I

ht htl

+ttt I

]t'TEN I

t l~

I n

ul <<

I lt ttt

\\(t ltt tg t

0.0

?5.0 1125 150.0 187.5 TIME (MINUTE) 225.0 300.0 AEP

'.".".'.Baielle Columbus Laboratories

LB/MI id'0 10 10 10 J

n (I

II

) <il )

t HYDROGEN 0.0 50.0

.= 100.0 150.0 200.0 250.0 300.0 400.0 TIME (MINUTE)

AEP

"..'Bamelle Columbus Laboratories

CONTAINNENT RESPONSE ANALYSES

~

CONTAINMENT GAS DISTRIBUTION AND PRESSURE TEMPERATURE LOADS FOR EACH OF THE THREE BASE SCENARIOS WILL BE CALCULATED WITH CLASIX

~

COMBUSTION PARAMETERS WILL BE CONSISTENT WITH PREVIOUS AEP ANALYSES

~

SENSITIVITY STUDIES

.'SSESS THE EFFECT OF FAN FAILURE (FOLLOWING FIRST LARGE BURN)

ON CONTAINMENT RESPONSE ASSESS THE EFFECT OF'ALTERNATE ROUTING OF REACTOR HEAD VENT LINE ON HYDROGEN DISTRIBUTION IN CONTAINMENT NARCH CALCULATED RESPONSE WILL PROVIDE A SCREENING PROCESS FOR MORE DETAILED ANALYSIS

~

IF GAS COMPOSITIONS ARE PREDICTED THAT INDICATE A LOCAL DETONATION IS POSSIBLES CONTAINMENT DYNAMIC LOADS WILL BE EVALUATED AEP

'.".".'Ballelle Columbus Laboratories

EVALUATION OF IGNITER EFFECTIVENESS

~

REVIEW CURRENT DATA BASE ON IGNITER EFFECTIVENESS IN THE PRESENCE OF SPRAYS AND OTHER COOLING EFFECTS

~

ESTIMATE CONTAINMENT FLOW PATTERNS AND MAGNITUDES OF HORIZONTAL VELOCITIES AT IGNITER LOCATIONS AEP

'".'.'BaNelle Columbus Laboratories

FINAL PRODUCTS OF ANALYSES

~

H2/H20 SOURCE TERMS TO CONTAINMENT FOR A RANGE OF SEVERE ACCIDENT SCENARIOS

~

CONTAINMENT PRESSURE TEMPERATURE LOADS FOR ACCIDENT SCENARIOS AND COMPARTMENT DIFFERENTIAL PRESSURES

~

ASSESSMENT OF THE EFFECTS OF RECIRCULATION FAN FAILURE

~

ASSESSMENT OF THE POTENTIAL FOR DEVELOPING DETONABLE COMPOSITIONS IF POSSIBLES FORCING FUNCTION FOR CONTAINMENT DYNAMIC ANALYSIS

~

ASSESSMENT OF IGNITER-EFFECTIVENESS UNDER SEVERE ACCIDENT CONDITIONS AEP

'.".".'.Batfelle Columbus Laboratories

KEY ITENS FOR NRC STAFF APPROVAL

~

6ENERAL APPROACH BEST ESTIMATE MODELLING PHYSICALLY COflS ISl ENT SCENAR IOS

~

SEQUENCE SELECTION

~

ANALYTICALTOOLS

~

COMBUSTION PARAMETERS

~

SCHEDULE AEP

'".".'.Battelle Columbus t.aboratortes

4 UPPER VOLUME

~

TOP DECK DOORS UPPER PLENUM LOWER VOLUME PRESSURIZER 0'0 0,

4 HP3

."a: ';.o.

O 4'.0

'0, D

INTER-MEDIATE DECK DOORS ICE BED LOWER PLENUM INLET DOORS 0

0 4

~ ~

O.

~ ~

0

~ 0 c

',Q.

~.Q e 'Q.QO+,, o'o PRESSURIZER RELIEF TANK

O'.P

'Q.'

.'0:G.:-'.: QO'~

0 "<:...

~ 0

.0:o.:'0 0'.

o~a'-

CP~.:

Ck.

'Qi',.

cia

~: ~ o (7.

~ 0 REACTOR VESSEL RECIRCU-LATION FAN STEAM GENERATOR g

o':.

o%,g'O.go'o: O. ~ "~+ ~

SIMPLIFIED DIAGRAM OF ICE CONDENSER CONTAINMENT COMPONENTS

Cg

INTERPRETATION OF THE FINAL RULE ON HYDROGEN CONTROL GROUND RULES FOR ANALYSIS MARK Te LEONARD BATTELLE COLUMBUS LABORATORIES AEP

".",'.Baftelle Columbus Laboratories

GENERAL ITEMS

~

INTENT IS TO ENSURE ADEQUACY OF EXISTING DESIGN

~

70TAL (INTEGRAL) HYDROGEN BURDEN IS FIXED ISSUE IS THE RATE AT WHICH IT IS ACHIEVED AND THE ACCOMPANYING STEAM RELEASE RATE RECOGNIZE THAT UNREALISTIC CORE MELT SCENARIOS MUST BE POSTULATED FOR SOME SEQUENCES AEP

'".".'.Battelle Columbus Laboratories

ACCEPTABLE ANALYSIS APPROACH BEST ESTIMATE (PHYSICALLY CONSISTENT)

FORMULATION

~

CURRENT Al/ALYTI CAL TOOLS FOR MODELLING SEVERE ACCIDENTS (NARCH, CLASIX) ARE SUFFICIENT

~

ENVIRONMENTAL CONDITIONS THAT EQUIPMENT MUST SURVIVE CAN BE DETERMINED BY EXAMINING SEVERAL ACCIDENT SCENARIOS THAT SPAN THE RANGE OF POTENTIAL HYDROGEN SOURCE TERMS

~

BIEI NETHODS FOR DETERMINING CONTAINMENT ULTIMATE STRENGTH

= ARE AN ACCEPTABLE ALTERNATIVE TO ASNE CODE CRITERIA

~

LOADS ON EQUIPMENT AND CONTAINMENT STRUCTURE NEED ONLY BE BASED ON DEFLAGRATION EVENTS IF DETONABLE COMPOSITIONS CAN BE SHOWN UNLIKELY AEP

".".::Hattelle Columbus Laboratories

I'a