ML20245L737

Forwards Request for Addl Info Re Pressure/Temp Limits. Response Requested within 45 Days of Ltr Date

ML20245L737
Person / Time
Site:	Brunswick
Issue date:	05/01/1989
From:	Tourigny E Office of Nuclear Reactor Regulation
To:	Eury L CAROLINA POWER & LIGHT CO.
References
TAC-71112, TAC-71113, NUDOCS 8905080122
Download: ML20245L737 (5)

Text

. . . ,

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• L May 1, 1989

.Dockst Nos. 50-325 DISTRIBUTION i

.and 50 324 a Docket

• File n. BGrimes(9A2)  !

Local PDR' DHagan (MNBB 3302) l Mr. Lynn W. Eury .

NRC PDR LSpessard(MNBB3701) {'

' Executive Vice President SVarga(14E) TNeeks (4)

Power Supply Glainas-Carolina Power & Light Company EAdensam WJones'(P_130))

EButcher (11F23 Post Office Box 1551 PAnderson ACRS(10)

Raleigh, North Carolina 27602 GPA/PA ETourigny(MNBC3302)

Edordan

Dear Mr. Eury:

ARM /LPMB

SUBJECT:

BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 - REQUEST FOR -

ADDITIONAL INFORMATION'. PRESSURE / TEMPERATURE-LIMITS (TAC NOS. 71112 AND 71113)

In conducting our review of your October 26 1988 and March 30, 1989, submittals relating to the above subject"at the Brunswick Steam Electric Plant, we have determined that we will need additional information identified in the enclosure to continue our review.

In order for us to maintain our review schedule, your response is requested within 45 days of. the.date of this letter.- If you cannot provide a full ,

response within the requested time, please provide your full reponse schedule within 30 days of the date of this letter.

The. reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.

.Please contact me at (301) 492-1474 if you have any questions concerning this letter.

Sin cerely ,

/5/

E. G. Tourigny, Senior Project Manager Project Directorate II-1 Division of Reactor Projects I/II

Enclosure:

As stated DFct' cc w/ enclosure:

See next page 1l

[BSEP12RAI] 8905080122 890501 "

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DATE :4/ /89

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0FFICIAL RECORD COPY

Mr. L.-W. Eury Brunswick Steam Electric Plant Carolina Power & Light Company Units l'and 2 i

cc: _

'Mr. Russell B. Starkey, Jr. Mr. J. L.. Harness.

Project Manager Plant General Manager iBrunswick Nuclear / roject Brunswick Steam Electric Plant P.'0. Box.10429 P.-0. Box 10429 Southport, North Grolina 28461 Southport, North 'arolina 28461

-Mr. R. E. Jones, General Counsel Mr..H. A. Cole Carolina Power & Light Company Special Deputy Attorney General P.- 0. Box 1551 State of North Carolina Raleigh, North Carolina 27602 P. O. Box 629 Raleigh, North Carolina 27602

%. Mark S. Calvert Associate General Counsel Mr. Robert P. Gruber Carolina Power & Light Company Executive Director P. O.. Box 1551 .

Public Staff'- NCUC Raleigh, North Carolina 27602 P. O. Box 29520 Raleigh, North Carolina 27626-0520 Ms. Grace Beasley, Board of Commissioteers P. 0. Box 249

. Bolivia, North Carolina 28422 Mrs. Chrys Baggett State' Clearinghouse Budget and Management-116 West Jones Street Raleigh, North. Carolina 27603 Resident Inspector U. S. Nuclear Regulatory Commission Star Route 1 P. O. Box 208 Southport, North Carolina 28461 Regional Administrator, Region II U. S. Nuclear Regulatory Commission

'101 Marietta Street, Suite 2900 Atlanta, Gecrgia 30323 Mr. Dayne H. Brown, Chief Radiation Protection Branch Division of Facility Services

.N. C. Department of Human Resources 701 Barbour Drive Raleigh, North Carolina 27603-2008 l

l l

ENCLOSURE i

REQUEST FOR ADDITIONAL INFORMATION ON PRESSURE / TEMPERATURE LIMITS CAROLINA POWER & LIGHT COMPANY BRUNSWICK UNITS 1 AND 2 DOCKET NO. 50-325 & 324 (1) The following questions relate to the hydrostatic and leak tests curve in Figure 3.4.6.1-3a in the October 26, 1988 submittal:

(A) How were pressure and temperature data points on the curve obtained?  !

Specifically, 298 psi at 70'F; 475 psi at 100'F; 750 psi and 1005 psi at 156*F; and 795 psi and 1092 psi at 164'F. How was the 15 psi instrument correction included in the pressure calculation? Provide detailed calculations on the above pressure / temperature data points and on the recirculation suction heatup portion of the curve.

(B) In the March 30, 1989 submittal (Page 10, top), CP&L calculated 1030 psig at 155.6'F and 1105 psig at 164.1*F. These two data points do not correspond to the data points in Figure 3.4.6.1-3a.

(C) At the bottom of the figure, footnote no. 6 incteates RTNDT = 56*F.

Should this t,a 70*F instead?  ;

(2) We cannot pinpoint the exact values of the following pressures in the Brunswick FSAR and in Figures 3.4.6.1-3a, 3b, and 3c:

(A) What is the hydrostatic pressure specified in the FSAR7 One section of the FSAR indicates 1.25 P design and another section of the FSAR indicates 1250 psig.

o .

L (B) What is the actual hydrostatic pressure used during hydrostatic' tests i at Brunswick units 1 & 2?

(C) Is the design pressure 1250 psig? Is the operating pressure 1000 psig?

(D) What is the leak test pressure used in Figures 3.4.6.1-3a. 3b, and 3c?

(3) Standard Technical Specifications for BWRs, NUREG-0123, Rev. 3, Section 3/4.4.6 (Page 3/4.4-17), states that reactor vessel flange and head flange temperature shall be verified.

The proposed Brunswick Tech. Spec. in the October 26, 1988 submittal did not include this surveillance requirement. Does CP&L verify the flange temperatures during heatups or cooldowns? Provide the reason if the answer is negative.

(4) CP&L should change the " proper revision" of Regulatory Guide 1.99 to

" Revision 2" shown in the. Bases section, page B3/4.4-4, in the October 26, 1988 submittal.

(5) Comparing the proposed Tech. Spec. (page 83/4.4-4) to the existing Tech.

Spec. (page B3/4.4-4), we found that a paragraph was completely missing from the proposed Bases section. The staff questions the deletion.

(6) In the March 30, 1989 submittal, CP&L indicated that the Brunswick feedwater nozzle heatup curve (Figure 3.4.6.1-1) was taken from the Hatch 1 and Fitz-patrick submittals but corrected for differences in the initial RT NDT' k

The staff compared the Fitzpatrick feedwater nozzle heatup curve with the j

-Brunswick curve. At the lower temperature range both curves are )

compatible but at a higher temperature range (i.e. at 175*F and higher) both j curves are mismatched. Provide detailed calculations on the construction of Figure 3.4.6.1-1.

1 1

4

4 q- t'^

1.

l 1

(7)' ~ The staff has 'the following two quastions on the page 9 calculation in the '

March 30,1989. submittal:

-(A) Should the pressure stresses at 450*F, 750*F, and 1020*F be 450 psi, 750 psi, and 1020 psi?

(8) Should the margin of 30.7 be 34 in the calculation of ART at 8 EFPY?

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