ML20129G791

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Summary of 960904 Meeting W/Cyap in Rockville,Md Re Licensee Evaluation That Concluded That Loads on SW Sys Would Be Unacceptable Following LOCA or MSLB Accident W/Concurrent LNP Event.List of Attendees Encl
ML20129G791
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 10/23/1996
From: Stephen Dembek
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9610300206
Download: ML20129G791 (22)
v • d • e


Text

_

. pa rto h  % UNITED STATES s* g NUCLEAR RECULATORY COMMISSION t WASHINGTON. D.C. 2056M001 October 23, 1996 LICENSEE: Connecticut Yankee Atomic Power Company

~

FACILITY: Haddam Neck Plant

SUBJECT:

SUMMARY

OF SEPTEMBER 4, 1996, MEETING REGARDING SERVICE WATER LOADS On Wednesday, September 4, 1996, a meeting was held at NRC Headquarters, between Connecticut Yankee Atomic Power Company (CYAPC0/ licensee) and the NRC staff. The purpose of the meeting was to discuss the licensee's evaluation that concluded that loads on the service water (SW) system would be unacceptable following a loss-of-coolant accident (LOCA) or main steam line break (MSLB) accident with a concurrent loss of normal power (LNP) event.

Attachment 1 is a list of meeting participants.

The meeting was organized into three areas: (1) a technical discussion on the LOCA/MSLB accident with a concurrent LNP event and its impact on the Haddam Neck SW and containment air recirculation (CAR) systems, (2) a technical discussion on the LOCA/MSLB event (no LNP) and its impact on the Haddam Neck SW and CAR systems, and (3) possible modifications at Haddam Neck to resolve the concerns The licensee began the meeting with a general description of the SW system and the line which feeds the CAR system. This included approximate lengths and elevation changes of piping runs, pipe size, interactions with other systems, heat exchanger size, and valve locations. The licensee then described the LOCA/MSLB accident with a concurrent LNP event analysis as it pertained to the SW and CAR systems. During the postulated event, the fans in the CAR units transfer heat to the stagnant SW system and create a significant steam void in the SW piping and in the tubes of the containment fan coolers. Upon restarting the SW pumps using the emergency diesel generators, the licensee concluded that the renewed SW flow would collapse the steam void and create a water hammer that could potentially cause piping and structural limits to be exceeded. l The licensee then described the same scenario except with no LNP event.

However, during this postulated event, since SW flow continues to the CAR system and the throttle valves in each SW line tend to suppress boiling, steam voids in the SW piping and in the tubes of the containment fan coolers would only exist for a short period of time. Therefore, the licensee concluded that the steam voids would collapse before any significant water hammer could 1 occur. Attachment 2 contains the slides the licensee used to describe this scenario.

hD \

l 9610300206 961023 PDR ADOCK 05000213 e ""  ;

NRC FA.E CENTER C8PY l

October 23, 1996 i

Finally, the licensee described a potential modification that would prevent -

the water hammer in the SW piping downstream of the CAR cooling coils from occurring in the first scenario. The design modification would include an accumulator that weuld have enough stored water to continue the flow of water through the SW system until the SW pumps are restarted off the emergency r diesel generators. Attachment 3 diagrams the potential modification the ,

licensee described. '

(Original Signed By)

Stephen Dembek, Project Manager Northeast Utilities Project Directorate Division of Reactor. Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-213 Attachments: 1. Attendance List

2. Slides used in presentation
3. Diagram of potential modification l

cc w/atts: See next page HARDCOPY Docket File PUBLIC PD 1-3 Memo i OGC ACRS E-MAIL FMiraglia/AThadani GHubbard RZimmerman LDudes SVarga BleFave JZwolinski JTappert PMcKee Alevin SDembek JGavula LBerry _

GHammer EJordan (JKR) KManoly John Fair TD'Angelo Mark Reinhart ASerkiz Beth WetzelL , JShapaker James Tatum WDean Tad Marsh JFRogge, RI )

DOCUMENT NAME: G: /)

n ...,,.,ini..so. \.DEMBEK\MEETSUM.9-4

. i . i. in. no : c . c.,y without .ti.cn+1n i< ,.u,. . copy itn .it. cam.ntioncio.or. m = No copy 0FFICE NUPD:PM .,l ,. PD2-2:LA M C NUP0 D' \ l l l NAME SDembek //) Q ('LBerry YL\' PMcfie DATE 10/92/96 10/t#/96 10([h/96

-0FFICIAL RECORD COPY

Ii .

Finally, the licensee described a potential modification that would prevent the water hammer in the SW piping downstream of the CAR cooling coils from occurring in the first scenario. The design modification would include an accumulator that would have enough stored water to continue the flow of water through the SW system until the SW pumps are restarted off the emergency diesel generators. Attachment 3 diagrams the potential modification the licensee described.

Step en Dembek, Project Manager Northeast Utilities Project Directorate Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-213 Attachments: 1. Attendance List

2. Slides used in presentation
3. Diagram of potential modification cc w/atts: See next page  ;

i I

i 4 .

Haddam Neck Plant 1

Lillian M. Cuoco, Esq. Mr. S. E. Scace, Vice President  !

i Senior Nuclear Counsel Nuclear Reengineering Implementation

Northeast Utilities Service Company Northeast Utilities Service Company P.O. Box 270 P.O. Box 128 Hartford, CT 06141-0270 Waterford, CT 06385 l Mr. Kevin T. A. McCarthy, Director Monitoring and Radiation Division Regional Administrator i Department of Environmental Protection Region I 79 Elm Street U.S. Nuclear Regulatory Commission j Hartford, CT 06106-5127 475 Allendale Road King of Prussia, PA 19406 Mr. Allan Johanson, Assistant Director Office of Policy and Management Board of Selectmen l Policy Development and Planning Division Town Office Building 80 Washington Street Haddam, CT 06438 Hartford, CT 06106 i Resident Inspector Mr. J. J. LaPlatney Haddam Neck Plant i

Haddam Neck Unit Director c/o U.S. Nuclear Regulatory Commission Connecticut Yankee Atomic Power Company 361 Injun Hollow Road 362 Injun Hollow Road

! East Hampton, CT 06424-3099 l

East Hampton, CT 06424-3099  !

Mr. A. M. Callendrello i

Mr. D. B. Miller, Jr. Licensing Manager - Haddam Neck i Senior Vice President North Atlantic Energy Service Corp.

Nuclear Safety and Oversight P.O. Box 300 1

Northeast Utilities Service Company Seabrook, NH 03874 P.O. Box 270 Hartford, CT 06141-0270 Mr. James S. Robinson Manager, Nuclear Investments and Mr. E. A. DeBarba Administration Vice President - Nuclear Technical Services New England Power Company j

Northeast Utilities Service Company 25 Research Drive P.O. Box 128 Westborough, MA 01582 Waterford, CT 06385 Mr. B. D. Kenyon Mr. F. C. Rothen President - Nuclear Group Vice President - Nuclear Work Services Northeast Utilities Service Company 4 Northeast Utilities Service Company P. O. Box 128 P.O. Box 128 Waterford, CT 06385 Waterford, CT 06385 Mr. Ted C. Feigenbaum Executive Vice President and Chief Nuclear Officer Northeast Utilities Service Company c/o Mr. Terry L. Harpster Director - Nuclear Licensing Services P.O. Box 128

, Waterford, CT 06385

e i MEETING BETWEEN CYAPCO AND NRC STAFF REGARDING SERVICE WATER LOADS SEPTEMBER 4. 1996  !

Mang Office James Andersen NRC/NRR/PM John Fair NRC/NRR/EMEB Mark Reinhart NRC/NRR/PDIII-I ,

Beth Wetzel NRC/NRR/PM i James Tatum NRC/NRR/SPLB l Tad Marsh NRC/NRR/SPLB George Hubbard NRC/NRR/SPLB Laura Dudes "/NRR/SPLB Bill LeFave 'NRR/SPLB John Tappert *

.,ARR/PECB Alan Levin SAC /NRR/SRXB James Gavula NRC/RIII/DRS Gary Hammer NRC/NRR/EMEB Kamal Manoly NRC/NRR/EMEB Tony D'Angelo NRC/NRR/PIPB Al Serkiz NRC/RES/GSIB Everett Perkins CYAPC0 Paul Mason CYAPC0 Paul Rothe Creare Inc.

Bob Fraser NSPS James Shapaker NRC/NRR/PGCB i

l Attachment 1

e CAR Fan Two-Phase Flow Dr. Paul H. Rothe

_I h6Cf6 , uto. 96-08-782

Service Water Cools Containment e Cold River Water i

e Pumped Through Gas-Liquid Heat Exchanger (CAR Fan) i e Throttled for Flow Control e Hot Water Returned to River Available for:

e Loss of Coolant Accident (LOCA) i e with . Loss of Normal Power (LNP) i e

@reare -

2 Mtg. 96-08-782

m Main Findings for CAR Fan Section 1

t i

-Overview -- 20 Hours e Throttle Limits, Suppresses Boiliug e No Boiling in CAR Fan e No Flashing at Throttie Inlet e No Flashing in Line e Flashing Discharge From Throttle Microview-- 100 Seconds e LOCA - A Void Builds, Slowly Collapses e LOCA/LNP - Same eeo,e ,

3 Mtg. 96-08-782 c ,

Variables for Transient Analysis h >

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@reare 4 Mtg. 96-08-782 i

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Calculations for Motor Heat Only, River at 95 F Creare CY APCO NOTE Calculations Results CAR fan Inlet " P "

Pressure (psia) 40.06 40.29 Temperature (*F) 95 95 Specified Flow Rate (gpm) 578.1 579.6 CAR fan Exit " X "

Pressure (psia) 24.16 24.27 Temperature ('F) 95 95 Flow Rate (gpm) 543.6 544.9 Motor Cooler Stream " M "

Temperature ('F) 100 Flow Rate (gpm) 34.6 34.65 Service Water Line " L "

Pressure (psia) 23.70 24.26 Temperature ('F) 95.3 95.3 Flow Rate (gpm) 578.1 579.55 Valve inlet " V **

Pressure (psia) 12.83 12.93 Temperature ('F) , 95.3 95.3 Flow Rate (gpm) 578.1 579.55 Valve Exit ** A **

Pressure (psia) 8.75 8.75 Specified

{ .

. 7 Mtg. 96-08-782

i Calculations for LOCA, River Water at 95 F Creare CY APCO Note Calculations Results CAR fan Inlet " P "

Pressure (psia) 49.25 Temperature ('F) 95 95 Specified Flow Rate (gpm) 497.2 CAR fan Exit " X "

Pressure (psia) 38.13 38.7 Temperature ('F) 256 256 Flow Rate (gpm) 467.5 449 Subcooling ('F) 6.7 Motor Cooler Stream " M "

Temperature (*F) 100 Flow Rate (gpm) 29.7 28 Service Water Line " L "

Pressure (psia) 37.81 38.7 Temperature (*F) 246.3 246.8 Flow Rate (gpm) 497.2 477 Subcooling ('F) 15.9 Valve Inlet " V "

Pressure (psia) 29.56 30.7 Temperature ("F) 246.3 246.8 Flow Rate (gpm) 497.2 477 Subcooling ('F) 2.1 Valve Exit " A "

Pressure (psia) irrelevant 8.7 Specified (choked) l

. 8 Mtg. 96-08-782

Values of Subcooling AT Sub t

Line 151 Line 154 _

Time X L V X L V 0 142.6 141.3 110.7 134.2 132.7 111.5 10 13.8 22.0 4.8 9.1 17.2 5.4 20 6.4 15.6 1.9 2.7 11.9 2.4 40 7.1 16.3 2.2 3.3 12.4 2.7 1

O. 9 Mtg. 96-08-782 i

Sensitivity to Valve Pressure Recovery Factor Valve Pressure Recovery Valve Flow Rate Valve Inlet Pressure Factor, Ft Qv (gpm) Py (psia) 0.85 497.2 29.56 0.75 491.5 30.48 0.65 483.3 31.77 0.55 471.0 33.66 0.45 451.5 36.52 0.35 419.0 40.99 1

10 Mtg. 96-08-782 i

i

The Thermal Wave Stage O Cold Water Flowing in bAR Fan Section LOCA Transient Heats CAR Fan Stage 1 Boiling Onset in About 12 Seconds Line Fills with Hot Water ,

Stage 2 Line Flow increases by 30%

Void Grows Pushing Out Water Hot Water Replaces Cold Downcomer Volds Stage 3 Hot Water Reaches Throttle Void Enters Run Stage 4 Thermal Profile Passes at Throttle Throttle Chokes Throttle Flow Declines Onset of Void Collapse Stage 5 Void Slowly Collapses Hot Water From CAR Fan Fills Void Stage 6 Throttle inlet Pressurizes Stable Choked Flow is Achieved -

CAR Fan Outlet is Subcooled, No Boiling 11 Mtg. 96-08-782 s

l

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- . Flow Rate of WaterThrough the Valve, O,

- Position of Leading Edge of Steam Column, S

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, 1. Maximum CAR Fan Heat Transfer

- No Degradation

- No Thermal inertia

2. Multiphase Flow Regime

- Segregated Flow Treated (No issue if Bubbly Flow in the Run) 3.No Steam Condensation on Pipe

4. Loss of Downcomer Head Neglected C 14 Mtg. 96-08-782

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