ML19318B696

Response to Intervenor Tx Pirg Ninth Set of Interrogatories. Includes Info Re Future Analysis of RCPB Piping Per ASME Code & Ebasco & GE Calculations.Affidavit & Certificate of Svc Encl

ML19318B696
Person / Time
Site:	Allens Creek File:Houston Lighting and Power Company icon.png
Issue date:	06/23/1980
From:	Copeland J, Newman J BAKER & BOTTS, HOUSTON LIGHTING & POWER CO., LOWENSTEIN, NEWMAN, REIS, AXELRAD & TOLL
To:	TEXAS PUBLIC INTEREST RESEARCH GROUP
References
NUDOCS 8006270327
Download: ML19318B696 (7)

Text

,

e 6/23/80 ,

n a \112

.y m s

iYT -

UNITED STATES OF AMERICA 2[ f ') -l

-f yJg g NUCLEAR REGULATORY COMMISSION j

- ~

BEFORE THE ATOMIC SAFETY AND LICENSING BOARD g ' ; ; Tg

/

In the Matter of f 3,

'y : E 5 ,---

HOUSTON LIGHTING & POWER N S

COMPANY $ Docket No. 50-466 5

(Allens Creek Nuclear 9 Generating Station, Unit S No. 1) $

APPLICANT 'S RESPONSE TO TEXPIRG' S NINTH SET OF INTERROGATORIES TO HOUSTON LIGHTING &

POWER COMPANY In response to the interrogatories propounded by Texas Public Interest Research Group, Inc., Houston Lighting

& Power (Applicant) answers as follows:

INTERROGATORY NO. 1:

With respect to computation of stress capabilities of reactor coolant boundary, respond to the following:

a. Where and by whom were the actual computer runs performed?

b. List each and every nuclear power facility for which computerized calculations were performed at the same time (i.e., during the same "run") as the calculations for the Allens Creek application?

c. Who developed the computer program software for the calculations relevant to the Allens Creek application?

d. Which other applicants for a nuclear power facility permit or license utilized the computer program stated in (c) above?

e. Has the calculations of stress relevant to the Allen Creek application been reviewed or re-examined within the last 18 months? If so, who conducted the review and what was the conclusion? Produce all documents resulting from such examinations.

l l

800627,0 -

r

f. Has HL&P or its agents ever re-calculated or re-run the computer operations? If so, state why the operation was performed again, and state any outcome which was different than that reached in the first operation.

g. List each and every document within HL&P's possession pertaining to this matter. Produce those documents.

ANSWER:

a. Ebasco will perform stress analysis for reactor pressure boundary piping according to ASME Section III Boiler and Pressure Vessel Code. The reactor and its internals, the recirculation loop, the main steam line and a portion of S/R valve discharge piping analysis is conducted by G.E. or its vendors.

b. Stress calculations within Ebasco's scope are not performed simultaneously for multiple plants. Each plant requires separate modeling of computer program input because of design differences. Stress calculations within GE's scope are performed for all BWR/6 plant whenever possible.

c. Ebasco uses an in-house developed computer program called PIFESTRESS 2010 for analysis of piping systems.

GE and its vendors utilize commercially available programs developed by GE and its venders. A listing of the GE programs used in stress and vibration analysis is contained in the NSSS GESSAR Appendix 5A. This lengthy appendix is available for inspection at EDC.

d. Concerning GE stress calculations, see response to (b). Stress calculations to be performed for ACNGS using the Ebasco model were performed for St. Lucie 1 and 2, Waterford 3, Shearon Harris 1,2,3,4 and WUPPS 3 and 5.

e. Applicant objects to this interrogatory on the grounds.of vagueness. Texpirg did not clarify what constitutes a " review" or "re-examination". The myriad stress calculations to be performed for ACNGS are ongoing by numerous contractors, vendors and sub-vendors. The completion of each step may be considered a review or examination.

Under this interpretation, the request is plainly unreason-able and over-burdensome. If TexPIRG can particularize a type of review or reviewer, Applicant will attempt to respond. I For example, Applicant can now respond that the NRC has not reviewed ACNGS stress calculations in the last 18 months.

I

~

n .

f. No.

g. The ACNGS PSAR and the NSSS GESSAR will be available for inspection and copying at the Energy Development Complex.

INTERROGATORY NO. 2:

How long is required for SCRAM of the reactor?

ANSWER:

See PSAR figure 15.1.1-1 INTERROGATORY NO. 3:

What is the nil ductility transition temperature for Allens Creek's reactor vessel?

ANSWER:

See PSAR section 5.2.4.6.8 INTERROGATORY NO. 4:

Will the operating temperature planned for Allens Creek be the same for the reactor throughout its lifetime?

If not, state what the operating temperature during the start-up year is, and the temperature at end of lifetime.

ANSWER:

Operating temperature is approximately 550*F throughout the lifetime of the Allens Creek RPV.

INTERROGATORY NO. 5:

Will irradiation of the reactor vessel shift the nil ductility transition temperature above its initial value? If so, what is the nature of the changes in ferritic metal that causes the shift?

ANSWER:

Yes. Radiation embrittlement.

INTERROGATORY NO. 6:

If (5) above is "yes", state the magnitude of the temperature shift in units of time and temperature.

ANSWER:

See Section 5.2.4.6.8 of the ACNGS PSAR.

INTERROGATORY NO. 7:

Do workpapers or documents relevant to #6 above exist in HL&P's possession?

If so, produce those documents, including any calculations used in responding to #6.

ANSWER:

See response to #6.

INTERROGATORY NO. 8:

State the pressure level set point for the actuation t

of each relief valve.

ANSWER:

Nine valves are set to relieve at 1123 psigs, nine at 1113 psig and one at 1103 psig.

INTERROGATORY NO. 9:

How much set point drift is anticipated for each relief valve?

ANSWER:

There are no established values for set point drift. Conservatism in the PSAR Chapter 15 analysis for over pressure transients is given in PSAR section 15.1.4.2.2.

Requirements for SRV surveillance will be delineated in the plant technical specifications.

Respectfully submitted,

., b!84(l- k:! C ..

OF COUNSEL: J// Gregory Ccpeland C'/ Thomas' Bi'ddle, Jr.

BAKER & BOTTS Charles G. Thrash, Jr.

3000 One Shell Plaza 3000 One Shell Plaza Houston, Texas 77002 Houston, Texas 77002 LOWENSTEIN, NEWMAN, REIS, Jack R. Newman AXELRAD & TOLL Robert H. Culp 1025 Connecticut Ave., N.W. 1025 Connecticut Ave., N.W.

Washington, D. C. 20036 Washington, D. C. 20036 ATTORNEYS FOR APPLICANT HOUSTON LIGHTING & POWER COMPANY THE STATE OF TEXAS 5 5

COUNTY OF HARRIS 5 BEFORE ME, the undersigned authority, on this day personally appeared L. D. Richards,. who upon his oath stated that he has answered the foregoing Applicant's Response to TexPRIG's Ninth Set of Interrogatories to Houston Lighting &

Power Company in his capacity as Lead Engineer for Houston Lighting & Power Company, and that all statements contained therein are true and correct to the best of his knowledge and belief.

'o L. D. Richards SUBSCRIBED and SWORN TO before me on this the 28 M day of ( j e h

, 1980.

/

s M =

N Nottary Public in and for' Harris County, Texas My Commissio

//- :2 S E$x /ires:

TB:07:K i

r i

I

i 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 6

(Allens Creek Nuclear Generating S Station, Unit 1) S CERTIFICATE OF SERVICE I hereby certify that copies of the foregoing Applicant's Response to TexPirg's Ninth Set of Interroga-tories to Houston Lighting & Power Company in the above-captioned proceeding were served on the following by deposit in the United States mail, postage prepaid, or by hand-delivery this 23rd day of June, 1980.

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

Atcmic Safety and Licensing Assistant Attorney General Board Panel for the State or 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 Judge, Austin County Washington, D. C. 20555 P. O. Box 99 Bellville, Texas 77418 Mr. 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 Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D. C. 20555

8 Steve Schinki, Esq. Carro Hinderstein Staff Counsel 609 Fannin, Suite 521 U.S. Nuclear Regulatory Commission Houston, Texas 77002 Washington, D. C. 20555 D. Marrack Mr. Bryan L. Baker 420 Mulberry Lane 1118 Montrose Bellaire, Texas 77401 Houston, Texas 77019 Mr. J. Morgan Bishop Stephen A. Doggett, Esq. 11418 Oak Spring P. O. Box 592 Houston, Texas 77043 Rosenberg, Texas 77471 Mr. John F. Doherty Robert S. Framson 4327 Alconbury Madeline Bass Framson Houston, Texas 77021 4822 Waynesboro Houston, Texas 77035 Ms. Brenda McCorkle 6140 Darnell Mr. W. Matthew Perrenod Houston, Texas 77074 4070 Merrick Houston, Texas 77025 Mr. Wayne E. Rentfro P. O. Box 1335 Mr. James M. Scott Rosenberg, Texas 77471 13935 Ivy Mount Sugar Land, Texas 77478 Mr. F. H. Potthoff 7200 Shady Villa, No. 110 Houston, Texas 77080

., TOl&W 75 t J. Gregory Copeland 1