ML20245B424

Responds to Request for Addl Info Re Pressure/Temp Limits for Plant

ML20245B424
Person / Time
Site:	Brunswick
Issue date:	06/13/1989
From:	Loflin L CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLS-89-171, TAC-71112, TAC-71113, NUDOCS 8906230173
Download: ML20245B424 (14)

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-JUN 131989 SERIAL: NLS-89-171 88TSB04 United States Nuclear Regulatory Commission l ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325.6 50-324/ LICENSE NOS. DPR-71 & DPR-62 RESPONSE TO. REQUEST FOR ADDITIONAL INFORMATION PRESSURE / TEMPERATURE LIMITS (NRC TAC NOS. 71112 AND 71113) j Centlemen: I LThe NRC requested additional information relating to Carolina Power &

Light Company's October 26, 1988 and March 30, 1989 submittals 1

concerning pressure / temperature limits for the Brunswick Steam Electric Plant, Units 1 and 2. Responses to the NRC questions are provided in l Enclosure 1.

Please re.fer any qt tions regarding this submittal to Mr. William R.

Murray at (919).546-4661.

Yours very.tru!y, I Leo . flin i l

Manag Nuclear Licens ng Section BAB/bab (\cor\ptlimits)

{

Enclosure cc: Mr. Dayne.H. Brown ,

Mr...S. D. Ebneter j Mr. W. M. Ruland Mr. E. C. Tourigny 8906230173 890613 I:"  !

PDR ADOCK 05000324 4 P PNU '

08 411 Fayetteville Street

• P. O. Box 1551

• Raleigh. N C 27602 m_

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ENCLOSURE l' BRUNSWICR STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50-325 6 50-324 OPERATING LICENSES DPR-71 AND DPR PRESSURE / TEMPERATURE LIMITS (NRC TAC NOS, 71112 AND-71113)

NRC OUESTION 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:

'NRC OUESTION 1(A) llow: vere 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.

CP&L RESPONSE TO OUESTION 1A Calculation for'298 psi at 70 F:

Design Pressure - 1250 psig Pre-service Hydrostatic Test Pressure - Design Pressure x 1.25

- 1563 psig 1563 psig x 0.20 - 313 psig 313 psig - instrument location correction - 313 - 15 psig - 298 psig Determination for 475 psi at 100 F:

'RTNDT f r Flange - 10 F Temperature Limit - RTNDT + SRP Value - 10 F + 90 F - 100 F The intersection of 100 F and the recirculation suction curve is at 475 F.

Determination for 750 psig and 1005 psig at 156 F:

The leak test pressure is 1005 psig. The intersection of the recirculation suction curve and the leak test curve occurs at a lower pressure of 750 psig at 156 F.

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Determination-for 795 psi'and 1092. psi at 164 F:

Inservice Hydrostatic Test Pressure - Leak Test Pressure x 1.10

- 1005 psig x 1.10

- 1105.5 psig 795 psig'is' identified as the intersection of the recirculation suction curve and hydro temperature.

.Section XI of the ASME Boiler and Pressure Vessel Code, Article

.IWB-5000 permits reduction in pressure based on test temperature. At

.100 F, the test pressure is 1.10 x operating pressure, and at 200 F, the test pressure is 1.08 x. operating pressure. Linear interpolation E of.the multipliers for a temperature of 164 F gives a multiplier of 1.087. Thus, Inservice Hydrostatic Test Pressure - Leak Test Pressure x 1.087

- 1005 psig x 1.087

- 1092 psig Inclusion of the Instrument Correction in the Pressure Calculation:

The leak and hydrotest temperature calculations were performed at 1020 and 1120 psig, respectively, to include the 15 psig pressure correction.

Calculation for the Recirculation Suction Heatup Portion of the Curve:

Calculation'for 550 psig (plotted at 535 psig for temperature correction):

Pressure Stress - 550 x 110 + 550 - 11458 + 275 - 11733 psi 5.28 2 Kip - 1.5 x M,x Pressure Stress - 2.17 x 11733 - 25461 psi in Kyp-2 Kip + K1T - 2 (25461) + 2000 - 52922 psi in where K 1T is fr m the WRC Bulletin 175.

T - 1p (52.922 - 26.777) + (.014493 x 66.3) - 2.52833 - 117 F

.. .014493 Calculation for 700 psig (plotted at 685 psig for temperature correction):

Ky - 65408 + 2000 - 67408 psi in where 2000 is from the WRC Bulletin 175 El-2 i

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h 4 T .ln.(f7.408 - 26.777) + (.014493 x 66.6) - 2.528 - 147 F

.014493 NRC OUESTION 1(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 3.4.5.1-3a.

CP&L RESPONSE TO OUESTION 1(B)

The two samplo calculations were performed for the overpressurization curve, not for the standard leak and hydrostatic tests. They include a 15 psig error correction.

NRC OUESTION 1(C)

At the bottom of the figure, footnote number 6 indicates RTNDT - 56 F.

Should this be 70 F instead?

CP&L RESPONSE TO OUESTION 1(C)

The RTNDT shown in Basis 6 is a misprint. It should be:

ART - (RTNDT)i + ARTNDT + Correction Correction - 2(.5 x 30.7) - 30.7 F ART'- 10 + 25.7 + 30.7 - 66 F The calculations were done with ART - 66 F.

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n NRC OUESTION 2 We cannot pinpoint the exact values of the following pressures in the l# Brunswick FSAR and in Figures'3.4.6.1-3a, 3.b, and 3.c:

NRC OUESTION 2(AT What is the hydrostatic pressure specified in;the FSAR? One section of the FSAR. indicates 1.25 x P design and another section of the FSAR indicates 1250 psig.

l, CP&L RESPONSE TO OUESTION 2(A)

The pre-service hydrostatic test pressure used at Brunswick was 1.25 x the design pressure.

NRC OUESTION 2(B)

What is the actual hydrostatic pressure used during hydrostatic tests at Brunswick, Units 1 and 27 CP&L RESPONSE TO OUESTION 2(B)

The design hydrostatic pressure test is performed at 1.25 x design pressure.

Thus, it occurred at 1563 psig. The in-service hydrostatic test is conducted at 1.10 x operating pressure, with the multiplier corrected for c

- temperature as specii'ied in Article IWB-5000 of the ASME Boiler & Pressure Vessel' Code. Thus, the in-service hydrostatic test is performed at 1092 psig.

NRC OUESTION 2(C)

Is the design pressure 1250 psig? Is the operating pressure 1000 psig?

CP&L RESPONSE TO OUESTION 2(C)

The design pressure is 1250 psig, and the operating pressure is 1005 psig.

NRC OUESTION 2(D)

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

CP&L RESPONSE TO OUESTION 2(D)

The leak pressure used in calculations for Figures 3.4.6.1-3a, 3b, and 3e is 1020 psig (operating pressure + 15 psig to allow for instrument error).

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NRC OUESTION 3-Standard' Technical Specifications for BWRs, NUREC-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 Technical Specification 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 angative.

CP&L RESPONSE TO OUESTION 3 g The reactor flange temperature is continuously recorded by means of two thermocouple in the flange region. The regions where the flange is controlling is specifically noted on the heatup.cooldown curves for the operators' guidance. Carolina Power & Light Company imposes a limit of 70 F on the flange temperature as opposed to the ASME limit of 10 F. The Company believes that the 60 F margin is sufficiently generous and, therefore, considers additional surveillance unnecessary.

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NRC OUESTION 4

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CP&L'should change the " proper revision" of Regulatory Guide 1.99 to l, " Revision 2" shown in the Bases section, Page B 3/4.4-4 in the i;. October 26, 1988 submittal.

CP&L' RESPONSE TO OUESTION 4

.CP&L prefers to use'" proper revision" because the NRC is already contemplating a Revision 3. By not being specific, we can avoid another Technical Specification revision of this sentence. The use of Revision 2 is noted on the graphs.

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NRC OUESTION 5 Compiring'the proposed Technical Specification (Page B 3/4.4-4) to the existing Technical Specification (Page B 3/4.4-4), we found that a paragraph was. completely missing from the proposed Bases section. The staff questions this deletion.

CP&L RESPONSE TO OUESTION 5 The paragraph was omitted because the methods of the Standard Review Plan provide conservative curves without resorting to the 3/4T calculations. A safety factor was added to core' region calculations for curves other-than hydrotest to give CP&L added assurance that the curves are conservative.

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NRC OUESTION 6 IIn t$e 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 Fitzpatrick submittals but corrected for differences in the initial RT NDT*

The staff compared the Fitzpatrick feedwater nozzle heatup curve with the Brunswick curve. At the lower temperature range, both c.urves are compatible but at a higher temperature range (i.e., at 175 F and higher) both curves

" are mismatched. Provide detailed calculations on the construction of Figure 3.4.6.1-1.

CP&L RESPONSE TO OUESTION 6 Above 175 F on Figure 3.4.6.1-1, the core region, represented by the recirculation suction metal temperature, becomes controlling. Therefore, a mismatch with the sister plants is to be expected as a result of different materials and radiation exposure. Note the intersection of the two curves at 175 F.

Calculations for points above 175 F are as follows:

1 At 600 psig (plotted at 585 psig to include temperature correction) 2 Kip - 2 x 2.19 x 12800 - 56 ksi in where Kip - Stress Intensity Factor caused by pressure.

Stress Intensity. Factor - K1 - 6.4 ksi in Reference Stress Intensity Factor - K1R-2 Kip +K1

- 56.1 + 6.4 - 62.5 ksi in T - In(62.5 - 26.777) + .014493 (81.4) - 2.52833 - 154 F

.014493 At 900 psig (plotted at 885 psig to include temperature correction)

I' 2 Kip - 2 x 2.195 x 19200 - 84.3 ksi in i K i - 6.4 ksi in K1R - 84.3 + 6.4 - 90.7 ksi in T - In(90.7 - 26.777) + .014493 (81.4) - 2.52833 - 194 F

.014493 At 1200 psig (plotted at 1185 psig to include temperature correction)

K1R - 2 x 2.4 x 25600 + 6400 - 129.3 ksi in T - In(129.3 - 26.777) - 1. 3486 - 226 F

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NRC OUESTION 7-The. staff 'has ' the following two questions of the Page 9 calculation in the March'30, 1989 submittal:

NRC OUESTION 7(A) i Should the pressure stresses at 450 F, 750 F, and 1020 F be 450 ps'i, 750 psi,.and 1020 psi?

IO CP&L RESPONSE TO OUESTION 7(A) j Yes, what was shown as "F should be written as psig.

[ .E NRC OUESTION 7(B)  !

Should the margin of 30.7~be 34 in the calculation of ART at 8 EFPY? i i

CP&L RESPONSE TO OUESTION 7(B) 1 No. Regulatory Guide 1.99, Revision 2, states that oA need not exceed one-half the mean value of the ARTNDT'

'l ARTNDT (surface) - 30.7-oA - .5 X 30.7.- 15.35 l

2aA - 2 x 15.35 - 30.7 i

Note that CP&L used the more conservative surface ARTNDT in this l case. )

l ADDITIONAL CP&L INFORMATION The upper temperature of the cross-hatched regions of Figures 3.4.6.1-2 for  !

BSEP-1 and,BSEP-2 were incorrectly located in the.Techntcal Specification j submittals. Corrected copies are included in Enclosure 2.

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.t ENCIASURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50-325 & 50-324 OPERATING L'ICENSES DPR-71 AND DPR-62 PRESSURE / TEMPERATURE LIMITS (NRC TAC NOS. 71112 AND 71113)

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' PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL l ':

-HYDROSTATIC AND LEAK TESTS

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70 80 90 100 tto 120 130 140 150 160 170 180 TEMPERATURE (' F)

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1. FUEL IN REACTOR

2. II. ACTOR NOT CRITICAL

3. REG. GUIDE 1.99 REY. 2 4 < 8 EFPY 1#

5. 3.5 X 10 N > 1 MEV

6. RT = 66*(1/4

/CHT)

7. ISSI INSTRIDENT LOCATION CORRECTION INCLUDED NOTES.

1. OPERATE To RIGHT AND/OR BELOW LIMITING LINES

2.

• INDICATES BOTE HEATUP AND C00LDOWN RATE

3. PRESSURE AND TEMPERATURE INTERSECTIONS NOTED BY PARENTHESES

4. OPERATING LIMIT INDICATES TEMPERATURE REQUIRED IF TEST PRESSURE WAS EXCEEDED.

BRUNSWICK - UNIT 1 3/4 4-17 A,nendment No.

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.. -(BSEP-1-129) i 'f FIGURE 3.4.6.1 2 PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL NORMAL OPERATION WITH CORE CRITICAL 1200 ,

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> 1 MEV B1.4 (1/4 T) j 5. 15hh!INSTRUMENTLOCATIONCORRECTIONINCLUDED '

6. REG. GUIDE 1.99 REV. 2  !

FOTES: i I 1. OPERATE TO RIGHT AND/OR BELOW LIMITING LINES

2.

• INDICATES BOTH HEATUP AND C00LDOWN RATE

3. PRESSURE AND TEMPERATURE INTERSECTIONS NOTED BY PARENTHESES

4. OPERATION IN CROSS-BATCHED AREA PERMITTED ONLY WHEN WATER LEVEL IS WITHIN NORMAL RANGE FOR POWER OPERATION.

BRUNSWICK - UNIT 1 3/4 4-16 Amendment No.

,., FIGURE 3.4.6.1-2 l, 7 PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL

.,~ NORMAL' OPERATION WITH CORE CRITICAL 1200 1100 e

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0 100 00 300 400 500 G00 I" (2 0) TEEMN (' F 1 'l BASES:

1. PUEL IN REACTOR

2. < 16 IFP

3. Y.1 X 10{ N/CM > 1 MEV 4 RT = 93 (1/4 T)

5. 15hkIINSTRUMENTLOCATIONCORRECTIONINCLUDED

6. REG. GUIDE 1.99 REV. 2 NOTFS:

1. OPERATE TO RIGHT AND/OR BELOW LIMITING LINES

2.

• INDICATES BOTH HEATUP AND C00LDOWN RATE

3. 7RESSURE AND TEMPERATURE INTERSECTIONS NOTED BY PARENTHESES 4 OPERATION IN CROSS-HATCHED AREA PERMITTED ONLY WHEN WATER LEVEL IS WITHIN NORMAL RANCE FOR POWER OPERATION.

BRUNSWICK - UNIT 2 3/4 4-16 Amendment No. l