ML19273C005

Applicant Response to Jf Doherty First Set of Interrogatories & Second Set of Requests for Documents. Affidavit & Certificate of Svc Encl

ML19273C005
Person / Time
Site:	Allens Creek File:Houston Lighting and Power Company icon.png
Issue date:	04/30/1979
From:	Copeland J, Newman J, Thrash C BAKER & BOTTS
To:
References
NUDOCS 7906180723
Download: ML19273C005 (16)

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UNITED STATES OF AMERICA 6 [ ;v NUCLEAR REGULATORY COMMISSION h(% '), V M[ 9 s de BEFORE THE ATOMIC SAFETY AND LICENSING BOARD -

In the Matter of: $

HOUSTON LIGHTING & POWER COMPANY $ Docket No. 50-466 (Allens Creek Nuclear Generating $

Station, Unit No. 1) $

APPLICANT'S RESPONSE TO "FIRST SET OF INTERROGATORIES AND SECOND SET OF REQUESTS FOR DOCUMENTS FROM JOHN F. DOHERTY TO HOUSTON LIGHTING AND POWER COMPAtW" In response to the interrogatories propounded by John F. Doherty, Houston Lightiftg & Power (Applicant) answers as follows:

INTERROGATORY NO. 1: What are the radiological consequence

[ sic] of an Anticipated Transient Without Scram (ATWS) using the currently planned safety rystems to mitigate its course?

ANSWER:

A. A preliminary generic assessment of the radiolo-gical consequences of an ATWS event is being prepared by General Electric Company in response to an NRC request for information.

It is estimated that these results will be available in May, 1979. Indications are that the results will be below 10 CFR Part 100 Limits.

2353 035 79061807J2jf '

B. None.

C. A. J. Levine, Manager Project Licensing 1, General Electric Company.

D. ATWS is a generic issue and is currently under-going review and resolution by the NRC. The ultimate resolution of this generic issue ennld affect the answer to this interroga-tory.

E. Not applicable.

F. Not applicable.

G. Not applicable.

INTERROGATORY NO. 2: What studies indicate the containment building steel shell will withstand pressur.e resulting from blowdown due to an ATWS?

ANSWER:

A. The containment building steel shell for Allens Creek has not been specifically analyzed for blowdown due to an ATWS event. A preliminary generic assessment of the containment atmospheric pressure is being prepared in response to a NRC request for additional information. It is estimated that these results will be available in May, 1979.

B. Ncne.

C. A. J. Levine, Manager Project Licensing 1, General Electric Company.

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A

D. See 1.D.

E. Not applicable.

F. Not applicable.

G. Not applicable.

INTERROGATORY NO. 3: What is the factor of conservatism against buckling of the containment steel shell during the dynamic loading with an ATWS blowdown?

ANSWER: '

A. The safety factor against buckling of the contain-ment building shell has not been caculated specifically for ACNGS. If a dynamic load from ATWS blowdown is identified in the generic study and required to be incorporated in the ACNGS design, it would be calculated using the safety factor criteria in Table 3.8-2 of the ACNGS PSAR.

B. See 3.A. This document is available for inspec-tion at the Applicant's Energy Development Complex, 12301 Kurland, Houston, Texas.

C. Jon White, Supervising Engineer, Houston Lighting

& Power. .

D. Not applicable.

E. Not applicable.

F.

Not applicable. 2353 037 G. Not applicable.

3

JNTERROGATORY NO. 4: What ATWS event gives the hignest pressure result in the coolant circulation system?

ANSWER:

A. According to the generic studies, a Main Steam Isolation Valve closure without reactor trip results in the highest pressure in the coolant system. No specific analysis has been made for Allens Creek.

B. Analysis of Anticipated Transients Without Scram, NEDO-10349, March, 1971. This document is available for inspec-tion at the Applicant's Energy Development Complex, 12301 Kurland, Houston, Texas.

C. A. J. Levine, Manager Project Licensing 1, General Electric Company.

D. Not applicable.

E. Not applicable.

F. Not applicable.

G. Not applicable.

INTERROGATORY NO. 5: What percent of the volume below the surface of the water in the reactor (under full power) is calculated to be bubbles?

ANSWER:

A. The core average void fraction (active coolant) is 0.428.

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B. Allens Creek Pi'liminary Safety Analysis Report, Table 4.4-1. This document is available for inspection at the Apy.licant's Energy Development Complex, 12301 Kurland, Houston, Texas.

C. Not applicable.

D. Not applicable.

E. Not applicable.

F. Not applicaole.

G. Not applicable.

INTERROGATORY NO. 6: Have you started to implement any plans for a rapid severe fuel failure detection system? (Rapid means faster than one minute).

ANSWER:

A. The Allens Creek design has always had the Main Steam Line Radiation Monitoring Subsystem which can detect severe fuel failure in less than one minute and isolate con-tainment.

B. Allens Creek Preliminary Safety Analysis Report, Section 7.1.2.1.11. See 3.B.

C. Not applicable.

D. Not applicable.

E. Not applicable.

F. Not applicable. 2353 039 G. Not applicable.

5

INTERROGATORY NO. 7: State the reliability of the Standby Liquid Control System (SLCS) and give the source of this infor-mation.

ANSWER:

A. The required quantitative reliability of the SLCS is defined in Nureg-0460, Vol. 3.

B. " Anticipated Transients Without Scram for Light Water Reactors," Nureg-0460, 1978. This document is available for inspection at the Applicant's Energy Development Complex, 12301 Kurland, Houston, Texas.

C. Not applicable.

D. Not applicable.

E. Not applicable.

F. Not applicable.

G. Not applicable.

INTERROGATORY NO. 8: State the source of your conclusion on Pg. 4.2-61 in the PSAR, that, "The SLCS shall be able to deliver enough sodium pentaborate (Na B 0 2 10 16 10 H2 O) solution into the reactor to insure reactor shutdown. What is the source of Fig.

4.2-24 in the PSAR?

ANSWER:

A. General Electric Standard Safety Analysis Report for 238 Nuclear Steam Supply System, Page 4.2-87 and Figure 4.2-24.

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B. See 8.A. This document is available for inspection at the Applicant's Energy Development Complex, 12301 Kurland Drive, Houston, Texas.

C. Not applicable.

D. Not applicable.

E. Not applicable.

F. Not applicable.

G. Not applicable.

INTERROGATORY NO. 9: How far above the bottom of the SLCS tank is the outlet to the reactor?

ANSWER:

A. The distance from the bottom of the existing SLCS storage tank to the top of the outlet connection to the reactor is 5.16" i .15".

B. Purchase Part Drawing 767E164, Revision 7, Sheet

1. A copy of this drawing is available for inspection at the Applicant's Energy Development Complex.

C. Jon White, Supervising Engineer, Houston Lighting

& Power.

D. Not applicable. ,

E. Not applicable.

F. Not applicable. 2353 041 G. Not applicable.

7

INTERROGATORY NO. 10: In the event the reactor vessel pressure rises above 1,400 psig, is it not true that the sodium penta-borate solution could not be injected into the system? If not true, why?

ANSWER:

A. If vessel pressure rises above 1,400 psig, the sodium pentaborate solution could not be injected into the system. Studies of the ATWS events (NEDO-10349) show that pressure in the coolant system would fall rapidly below this value due to recirculation pump trip. Hence, by the time the SLCS would be called on to inject boron, system pressure would be such that it could not prevent boron injection.

B. Analysis of Anticipated Transients without Scram, NEDO-10349, March, 1971. This document is available for inspec-tion at the Applicant's Energy Development Complex, 12301 Kurland, Houston, Texas.

C.

D. Not applicable.

E. Not applicable.

F. Not applicable.

G. Not applicable.

INTERROGATORY NO. 11: Why is the SLCS not designed to automat-ically start in event of entire bank of control rods insertion failure?

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A. In event of failure of the rod of maximum worth to insert?

B. In event of failure of two or more rods of maxi-mum worth to insert?

ANSWER:

A. The SLCS is not presently designed to mitigate an ATWS event. Consequently, automatic starting is not required.

It is possible that the generic resolution for ATWS will require design changes for SLCS, including automatic starting.

B. See 7.B.

C. Jon White, Supervising Engineer, Houston Lighting

& Power.

D. See 1.D.

E. Not applicable.

F. Not applicable.

G. Not applicable.

INTERROGATORY NO. 12: What is your estimate of cost increase to implement Alternative #4 as proposed for "New Plants" in NUREG-0460, v.III?

ANSWER:

A. Applicant agrees with the estimate of costs contained in Nureg-0460, Vol. III, Appendix E.

.c .

B. See 7.B.

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C. Jon White, Superv.cing Engineer, Houston Lighting

& Power.

D. Not applicable.

E. Not applicable.

F. Not applicable.

G. Not applicable.

INTERROGATORY NO. 13: What equipment is located below the SLCS storage and test tanks in Fig. 1.2-8 from the PSAR? (Sorry, print too small in Fig.).

ANSWER:

A. Hydraulic Control Unit Modules.

B. ACNGS PSAR, Figure 1.2-8. See 5.B.

C. Jon White, Supervising Engineer, Houston Lighting

& Power.

D. Not applicable.

E. Not applicable.

F. Not applicable.

G. Not applicable.

INTERROGATORY NO. 14: Have you determined what space for a "high capacity liquid poison injection system" (SEE NUREG-0460, V. III, Table I, Page 18) will be needed?

A. Is current space sufficient?

B. How many more than 3,840 gals. of 13.4% sodium pentaborate solution will be required for conformance to alter-native #4 as listed in NUREG-0460 (See above).

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ANSWER:

A. Applicant has no reason to believe that current space will be insufficient based on its knowledge of what it expects will be required. The capacity of the SLCS should not change from the present design of 5,150 gallons regardless of which ATWS design alternative is chosen.

B. Standby Liquid Control System, System Design Description, Table 2.3-2. This document is available for inspection at the Applicant's Energy Development Complex, 12301 Kurland Drive, Houston, Texas.

C. Jon White, Supervising Engineer, Houston Lighting

& Power.

D. Not applictble.

E. Not applicable.

F. Not applicable.

G. Not applicable.

INTERROGATORY NO. 15: Has Applicant attended any of the Advisory Committee on Reactor Safeguard meetings on ATWS in the past year?

A. List the most recent? [ sic]

ANSWER:

A. Yes. Advisory Committee on Reactor Safeguards ATWS Subcommittee Meeting, August 1, 1978.

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B. Not applicable.

C. Jon G. White, Supervising Engineer, Houston Lighting & Power.

D. Not applicable.

E. Not applicable.

F. Not applicable.

G. Not applicable.

INTERROGATORY NO. 16: Have you committed at this time to the Alternative #4 solution to the ATWS problem?

ANSWER:

A. Applicant has committed to adopt the generic resolution of ATWS and to not preclude the ATWS design alterna-tives discussed in NUREG-0460.

B. ACNGS PSAR, Appendix K, NRC Question 032.2. See 5.B.

C. Not applicable.

D. Not applicable.

E. Not applicable.

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F. Not applicable.

G. Not applicable.

Respectfully submitted, 3regorg Copelan#

J les G". TIM; ash 3 0 One Shell Plaza ston, Texas 77002 Of Counsel: Jack R. Newman Baker & Botts Robert H. Culp 3000 One Shell Plaza 1025 Connec",icut Ave., N.W.

Houston, Texas 77002 Washington, D.C. 20036 Lowenstein, Newman, Reis, Attorneys for Applicant Axelrad & Toll HOUSTON LIGHTING & POWER COMPANY 1025 Connecticut Ave., N.W.

Washington, D.C. 20036 2353 047 13

THE STATE OF TEXAS S S

COUNTY OF HARRIS S BEFORE ME, THE UNDERSIGNED AUTHORITY, on this day personally appeared J. G. White, who upon his oath stated that he has answered the foregoing Houston Lighting & Power Company's Answers to First Set of Interrogatories and Second Set of Requests for Documents from John F. Doherty in hic capacity as Supervising Engineer for Houston Lighting and Power Company, and all statements contained therein are true and correct to the best of his knowledge and belief.

k b]b JfG." White' SUBSCRIBED AND SWORN TO BEFORE ME by the said J.

G. White, on this Sop)_, day of h *L , 1979.

v LM N6rtary Public in and for Harris County, Texas 2353 048

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of S S

HOUSTON LIGHTING & POWER COMPANY S Docket No. 50-466 S

(Allens Creek Nuclear Generating S Station, Unit 1) S CERTIFICATE OF SERVICE I hereby certify that copies of the foregoing Applicant's Answers to First Set of Interrogatories and Second Set of Requests for Documents from John F. Doherty in the above captioned proceeding were served on the following by deposit in the United States mai , p stage prepaid, or by hand delivery this 2k7/$ day of , 1979.

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Sheldon J. Wolfe, Esq., Chairman Richard Lowerre, Esq.

Atomic Safety and Licensing Assistant Attorney General Board Panel for the State of Texas U.S. Nuclear Regulatory Commission P. O. Box 12548 Washington, D. C. 20555 Capitol Station Austin, Texas 78711 Dr. E. Leonard Cheatum Route 3, Box 350A Hon. Charles J. Dusek Watkinsville, Georgia 30677 Mayor, City of Wallis P. O. Box 312 Mr. Gustave A. Linenberger Wallis, Texas 77485 Atomic Safety and Licensing Board Panel Hon. Leroy H. Grebe U.S. Nuclear Regulatory Commission County Jadge, Austin County Washington, D. C. 20555 P. O. Box 99 Beilville, Texas 77418 Chase R. Stephens Docketing and Service Section Atomic Safety and Licensing Office of the Secretary of the Appeal Board Commission U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, D. C. 20555 Washington, D. C. 20555 R. Gordon Gooch, Esq. Atomic Safety and Licensing Baker & Botts Board Panel 1701 Pennsylvania Avenue, N. W. U.S. Nuclear Regulatory Washington, D. C. 20006 Commission Washington, D. C. 20555 2353 049

Steve Sohinki, Esq.

Staff Counsel U. S. Nuclear Regulatory Commission Washington, D. C. 20555 John F. Doherty 4438 1/2 Leeland Houston, Texas 77023 Madeline Bass Framson 4822 Waynesboro Drive Houston, Texas 77035 Robert S. Framson 4822 Waynesboro Drive Houston, Texas 77035 Carro Hinderstein 8739 Link Terrace Houston, Texas 77025 D. Marrack 420 Mulberry Lane Bellaire, Texas 77401 Brenda McCorkle 6140 Darnell Houston, Texas 77074 F. H. Potthoff, III 1814 Pine Village Houston, Texas 77080 Wayne E. Rentfro P. O. Box 1335 Rosenberg, Texas 77471 James M. Scott, Jr.

8302 Albacore Houston, Texas 77074 M-

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