ML20141K652

Forwards Request for Addl Info Re Review of Plant,Unit 1 1996 SG Tube Insp 90 Day Rept

ML20141K652
Person / Time
Site:	Beaver Valley
Issue date:	05/23/1997
From:	Brinkman D NRC (Affiliation Not Assigned)
To:	Cross J DUQUESNE LIGHT CO.
References
TAC-M96250, NUDOCS 9705290274
Download: ML20141K652 (5)

Text

'

<  % May 23, 1997 l

Mr. J. E. Cross President-Generation Group Duquesne Light Company Post Office Box 4 Shippingport, PA 15077

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING REVIEW 0F BEAVER VALLEY POWER STATION, UNIT N0. 1 (BVPS-1), 1996 STEAM GENERATOR TUBE INSPECTION 90-DAY REPORT (TAC NO. M96250)

Dear Mr. Cross:

By letter dated August 2, 1996, Duquesne Light Company (DLC) submitted for NRC staff review a copy of the " Beaver Valley Unit 1 1996 Alternate Repair Criteria 90 Day Report." This report was submitted to satisfy a commitment as a part of implementing the voltage-based alternate repair criteria in the BVPS-1 technical specifications. The NRC staff has initiated its review of the subject report but has determined that additional information is required to complete our review. The additional information that is required is identified in the enclosed RAI. DLC is requested to provide this additional information within 30 days of receipt of this letter to enable the NRC staff to complete its review within a timely manner.

Should you have any questions on this matter, please contact me on (301) 415-1409.

Sincerely,

/s/

Donald S. Brinkman, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-334 l l

Enclosure:

RAI '

cc w/ encl: See next page DISTRIBUTION: l Docket File ACRS, TWF JTsao l

PUBLIC M0'Brien PEselgroth, RI '

PDI-2 r/f DBrinkman ESullivan SVarga 0GC, 0-15B18 JStrosnider 0FFICE PDI-2/PM n m PDI-2/LA.., PDIh2/D l NAME DBrinkma N M0'dYien JS b DATE E /23/97 )f3/97 .(/D97 l OFFICIAL RECORD CD)Y l DOCUMENT NAME: BV96250.RAI hhh h hkb b 2 9705290274 970523 PDR ADOCK 05000334 G PDR

, w

• W%

b y* 1 ,

UNITED STATES

}

NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001

\ . . . . . ,o# May 23, 1997 Mr. J. E. Cross President-Generation Group Duquesne Light Company Post Office Box 4 Shippingport, PA 15077

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING REVIEW 0F BEAV VALLEY POWER STATION, UNIT NO. 1 (BVPS-1), 1996 STEAM GENERATOR TUBE INSPECTION 90-DAY REPORT (TAC N0. M96250)

Dear Mr. Cross:

By letter dated August 2, 1996, Duquesne Light Company (DLC) submitted for NRC staff review a copy of the " Beaver Valley Unit 11996 Alternate Repair Criteria 90 Day Report." Thi", report was submitted to satisfy a commitment as a part of implementing the voltage-based alternate repair criteria in the BVPS-1 technical specifications. The NRC staff has initiated its review of the subject report but has determined that additional information is required to complete our review. The additional information that is required is identified in the enclosed RAI. DLC is requested to provide this additional information within 30 days of receipt of this letter to enable the NRC staff to complete its review within a timely manner.

Should you have any questions on this matter, please contact me on (301) 415-1409.

Sincerely, n f. &

Donald S. Brinkman, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-334

Enclosure:

RAI cc w/ encl- See next page l

\

.: s e i l

s  !

J. E. Cross Beaver Valley Power Station Duquesne Light Company Units 1 & 2

! cc:

i Jay E. Silberg. Esquire Bureau of Radiation Protection l Shaw Pittman Potts & Trowbridge Pennsylvania Department of  !

2300 N Street. NW. Environmental Resources i Washington, DC 20037 ATTN: Michael P. Murphy l Post Office Box 2063 i Director-Safety and Licensing Harrisburg PA 17120 l Department (BV-A) j i Duquesne Light Company Mayor of the Borrough of l Beaver Valley Power Station Shippingport i PO Box 4 Post Office Box 3 i Shippingport PA 15077 Shippingport. PA 15077 l Commissioner Roy M. Smith Regional Administrator. Region I West Virginia Department of Labor U.S. Nuclear Regulatory Commission i Building 3. Room 319 47.5 Allendale Road l Capitol Complex King of Prussia. PA 19406 Charleston, WVA 25305 Resident Inspector

, Director, Utilities Department U.S. Nuclear Regulatory Commission  !

l Public Utilities Commission Post Office Box 298 180 East Broad Street Shippingport. PA 15077 Columbus OH 43266-0573 i

~

Director. Pennsylvania Emergency Duquesne Light Company

, Management Agency Beaver Valley Power Station l Post Office Box 3321 PO Box 4 Harrisburg, PA 17105-3321 Shippingport. PA 15077  ;

l ATTN: S. C. Jain. Vice President Ohio EPA-DERR Nuclear Services (BV-A) i ATTN: Zack A, Clayton Post Office Box 1049 Columbus OH 43266-0149 Dr. Judith Johnsrud National Energy Committee l Sierra Club l 433 Orlando Avenue State College PA 16803 I

I Duquesne Light Company ,

Beaver Valley Power Station i PO Box 4 Shippingport, PA 15077 ATTN: R. L. Grand. Division Vice

! President. Nuclear Operations Group

and Plant Manager (BV-SOSB-7)

L e

- ~ . _ - - . . . - - - . . - . -. . - . - - . . . . - . - - . ~ - - - .-

. L l

Eg i

REQUEST FOR ADDITIONAL INFORMATION REGARDING REVIEW 0F 1996 STEAM GENERATOR TUBE INSPECTION 90-DAY REPORT BEAVER VALLEY POWER STATION. UNIT NO. 1 (BVPS-1)

DOCKET NO. 50-334 By letter dated August 2,-1996, Duquesne Light Company submitted for NRC staff l review the report: " Beaver Valley Unit 1,1996 Alternate Repair Criteria 90  !

Day Re) ort." As a result of a review of this document, the NRC staff requests l that tie licensee provide responses to the following questions and comments in i order for the staff to assess differences between the analytical results in i the report and results generated by the staff.

1. Provide the key assumptions.and input data in the calculations of the '

projected voltage distribution for the end of cycle (E0C) 12, specifically: '

(a) Is interpolation between voltage bins performed; i (b) Is Equation 3.5 or 3.6 in the Westinghouse report, WCAP-14277, used; l (c) When a random sample of probe wear exceeds the probe wear cutoff, is the probe wear distribution randomly sampled until a'value less than the cutoff is obtained or is the cutoff value assumed;

', (d) Is the non-destructive examination uncertainty adjustment applied to i the beginning-of-cycle (B0C) voltage only or to the sum of the B0C l Voltage and the growth rate;

' (e) What method is used to account for the fractional indications- I (f) Confirm that the projected voltage distribution for cycle 12 shown  !

l in Table 6-2 of the 90-day report was calculated based on the growth 1 l

rates shown in Table 3-6.

2. In the calculation of the probability of burst and the primary-to-secondary leakage under postulated accident conditions, discuss how l fractional indications were accounted (e.g., 7.3 indications, 0.002 l indications).

3. Provide the input data for the leak rate analysis as shown in Table 7-2 of the 90-day report, including parameters for leakage correlation and L probability of leak (POL) calculations. Specifically, (a) the intercept, slope, and standard error of the lea )

data points; (c) sum of (Xi - X bar)p,rate mean data;of X,(b) andnumbersum of of X2 of leak therate leak rate data, where "X" is the log of the bobbin voltage; (c) " slope",  !

l

-" intercept", and mean square error of the POL data; (d) number of POL data points;' and (e) the values of the covariance matrix of the i coefficients Beta (Vn , V33, V 22 ) of the regression equation. '

. l 1

Enclosure 1 i

l l

. .i 2- '

4. Provide the in)ut data for the probability of burst analysis as shown.in Table 7-2 of tie 90-day report. Specifically, (a) mean, standard deviation, and normalization value of the tube material property; (b) slope, intercept, and standard error of the burst pressure d numberofburst,pressuredatapoints;(d)sumof(X-Xbar)gta;(c) , mean of X, and sum of X of the burst data points; where X is the log of the bobbin voltage.

5. The projected voltage distribution for the end of cycle 12 is presented in table 6-2 of the 90-day report. The values of indication for some voltage bins seem to be inconsistent. For example, for steam generator A, the indications for 2.5 volts, 2.6 volts, and 2.7 volts are 0.71, 0.04, and 0.70, respectively. Verify the indications values in Table 6-2.

6. The staff has used in its calculations the pulled tube data in Table 5-2 of the EPRI report, " Steam Generator Tubing Outside Diameter Stress Corrosion Cracking at Tube Support Plates Database for Alternate Repair Limits-1996 Database Update," NP-7480-L November 1996. The licensee referenced the June 1996 edition of the same EPRI report in its 90-day report. The staff is not clear if the licensee used the same p.:1hd tube data as the data set used in the staff calculations, considering the recent pull tube data that have been made available in the industry.-

Also, there are some pulled tube data from French plants that have been excluded from the data set in the November 1996 edition of the EPRI report. The licensee is requested to provide the data points of pulled

' tubes that it used in its calculation, preferably, in a format similar to Table 5-2 in the November 1996 edition of the EPRI report.

I I

i 1

e