ML20094A592
| ML20094A592 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 07/19/1984 |
| From: | TELEDYNE ENGINEERING SERVICES |
| To: | |
| Shared Package | |
| ML20094A596 | List: |
| References | |
| TR-6052-1, TR-6052-1-R02, TR-6052-1-R2, NUDOCS 8408060016 | |
| Download: ML20094A592 (26) | |
Text
{{#Wiki_filter:BOSTON EDISON CO. 25 BRAINTREE HILL OFFICE PARK BRAINTREE, MASSACHUSETTS 02184 TECHNICAL REPORT TR-6052-1, REV. 2
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PILGRIM NUCLEAR POWER STATION REACTOR PRESSURE VESSEL PRESSURE TEMPERATURE LIMITS JUL Y 19,1984 O 1 WTELEDYNE ENGINEERING SERVICES 130 SECOND AVENUE WALTHAM, MASSACHUSETTS 02254 7 8408060016 840730 617-8 9 3350 PDR ADOCK 05000293 P PDR
n . TE WE ENGNEERNG SERVICES Technical Report TR-6052-1, Rev. 1 'Z) ') TABLE OF CONTENTS PAGE n
1.0 INTRODUCTION
1 2.0 REACT 0F, VESSEL FRACTURE TOUGHNESS PROPERTIES 1 2.1 Reference Temperature, RT 2 NDT -) . 2.1.1 Beltline 2 2.1.2 Closure Region and Shroud Support Region 4 2.1.3 Feedwater Nozzle 5 2.2 Upper Shelf Energy 5 2.2.1 Beltline 6 2.2.2 Closure Region, Shroud Region, F-W Nozzle 6 3.0 OPERATIONAL LIMITS 7 3.1 Closure Region 7 3.2 Shroud Support Region 9 3.3 Beltline 9
, 3.3.1 End-0f-Life 9 3.3.2 Intermediate Operational Periods 10 3.4 Feedwater Nozzle 11 4.0 PRESSURE-TEMPERATURE LIMIT CURVES 11
?
5.0 REFERENCES
12 O APPENDIX A - EXAMPLE CALCULATIONS APPENDIX B - P-T PLOTS c) _
W TELEDYNE ENGINEERING SERVICES Technical Report TR-6052-1, Rev. 1 @
1.0 INTRODUCTION
g Coston Edison Co. (BEC0) has requested Teledyne Engineering Services (TES) to provide an assessment of the compliance of the Pilgrim NPS Reactor Pressure Vessel (RPV) with the recently amended requirements of 10CFR50, Appendix G (Reference 1). O This report addresses the requirements of Paragraph IV of Appendix G relative to the pressure-temperature (P-T) limits for the RPV. The current Technical Specification limits were developed for the Pilgrim RPV in 1976 g (Reference 2). Reported herein is an assessment of the impact on the current P-T limits of the Paragraph IV requirements as they appear in the current amendment to Appendix G. 2.0 REACTOR VESSEL FRACTURE TOUGHNESS PROPERTIES Appendix G imposes the fracture toughness testing requirements of Section III, Winter 1981 (Reference 3) and therefore, requires compliance g with NB-2322 with regard to Charpy V-notch specimen orientation and loca-tion. For plate and forging product forms, NB-2322 requires C yspecimens to be oriented in a direction normal to the principal rolling direction, that is, the weaker direction. For older plants in which current specimen orientation requirements may not have been imposed, USNRC Branch Technical Position MTEB 6-2 (Reference 4) provides procedures for estimating transverse impact g properties from longitudinally-oriented specimens. These are stated as follows: The temperature at which 50 f t-lbs and 35 mils would have been ob-D tained on transverse specimens may be estimated by one of the following criteria: 0 _ . . . . .. . )
g_) TE WE ENGINEERING SERVICES Technical Report - TR-6052-1, Rev. 1 (a) Test results from longitudinally oriented specimens reduced to 65% of their value D (b) Temperatures at which 50 f t-lbs and 35 mils were obtained on longitudinally oriented specimens increased by 20F No adjustment for drop weight tests are required, although the Charpy adjustment may affect RT NOT* TES has reviewed the available impact test data for the Pilgrim RPV and applied the MTEB 5-2 adjustments where required. The resulting RT NDT C and upper-shelf energy levels are then determined for use in establishing P-T limits. 2.1 Reference Temperature, RT
.9DT 2.1.1 Beltline The Combustion Engineering (CE) Material Certification Reports (Reference 5) state that specimens were taken parallel to the major rolling direction of the plate at the 1/4 thickness level. Therefore, an adjustment to the Charpy impact data is required.
Applying this criteria to the CE base metal test results for the unfrradiated beltline specimens result in the following (Note: Tabulation represents test temperature at 50 ft-lbs/35 mils): TNDT + 60F CE Adjustment Criteria Man DE NDT T C-V (a) (b) NOT
-30 10/-6 48/50 30/14 -10*
-40 22/16 56/50 42/36 -4
-20 13/-1 67/52 33/19 -3 y *See Appendix A for Example Calculation.
E l M F W NE ENGdNEERING SERVCES Technical Report ( TR-6052-1, Rev. 1 - The dropweight T NDT indicated by the Material Certifica-tion Reports are also tabulated above. For transverse specimens the above
-)
Charpy levels would have to be attained for a test temperature no greater Since this is not the case, RT is taken as -3F than DWTNDT + 60F. NDT (57-60) for the base metal.
.)
Drop weight data for the weld and HAZ are not available. MTEB 5-2 provides for estimating TNDT from full Charpy V-notch curves. For SA-533 Grade B, Class 1 plate and weld metal, T NDT may be assumed to be the temperature at 30 ft-lbs or 0F, whichever is higher. Southwest Research Institute (swr) provides weld metal and HAZ Charpy impact data (Reference 6) for unirradiated beltline ma-terial. Applying the 30 f t-lbs criteria to the swr data gives T NDT as the greater of the following or 0F: Weld Metal: -120F* HAZ : - 70F swr (Reference 6) also provides the predicted adjustment to RT NDT over 32 effective full power years (EFPY) due to irradiation. Accounting for the base metal adjustment for specimen orientation the following values apply to the beltline at the 1/4 thickness location: RT NDT ART NDT Initial 32 EFPY Base Metal 62F 0 62F Weld Metal 136 0 136 _ liAZ 62 0 62 No adjustment has been made to the HAZ Charpy data since neither MTEB 5-2 nor ASTM E185 specifically requires such an adjustment. 3
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lO TTiri m(NE l ENGNEERING SERVICES Technical Report TR-6052-1, Rev. 1 O In addition, the tabulation reflects a RTNDT shif t equal to that of the base material, even though Reference 6 reports this shif t to be negligible g for the HAZ. 2.1.2 Closure Region and Shroud Support Region The Combustion Engineering Material Certification g Reports for the head torus plates, the upper shell plates and the lower shell plates indicate that impact specimens were taken parallel to the major rolling direction. Applying the MTEB 5-2 adjustment for orientation O gives the following: T TNDT + 60F NOT Adjusment Criteria O CE (a) (b) (a) (b) Head -11/-17 14/12 9/3 -46 -51 22/12 47/43 42/32 -13 -18 O Upper Shell - 3/-15 56/55 17/5 -4 -43 35/11 75/68 55/31 15 -5 18/0 59/40 38/20 -1 -22 O Lower Shell 20/5 62/48 40/25 2 -20 32/20 72/60 52/40 12 -8 34/15 77/55 54/35 17 -6 O The CE drop weight test data for the head, upper shell and lower shell material indicates no break at -10F. Since TR-2318 uses an RT NDT of -10F for the head, the pressure temperature limits determined therein are ap-O propriate for trar - Impact properties of the head. For the upper shell, the 50 ft-16 ,~ mil) requirement for one specimen is met at a TNDT of -5f (Adjustment Criteria (b)). Therefore, the TR-2318 results are O
7
- mus ENG2EERING SERVICES Technical Report TR-6052-1, Rev. 1 adjusted to an RTNDT of -5F. For the lower shell, TR-2318 conservatively uses an RTNDT of +40F whereas the Charpy data above indicates the trans-verse RT NDT to be -6F. The TR-2318 results are adjusted to account for this effect, also.
2.1.3 Feedwater Nozzle The CE Material Certification Reports do not indicate impact specimen orientation. Assuming standard procedures of the period were consistent with SA-370, it is assumed that a longitudinal orientation was used since SA-370 specifies longitudinal orientation unless otherwise specified. Applying the MTEB 5-2 procedures to the CE impact data gives the following: TNDT + 60F Maximum Adjustment Criteria T CE (a) (b) NDT
-28/-40 14/0 -8/-20 -46 The CE drop weight test data indicates no break at 10F. This is also the RT NDT value used in TR-2318. Therefore, the results therein for the feedwater nozzle are considered appropriate for transverse impact proper-ties, i 2.2 Upper Shelf Energy An adjustment to upper shelf energy to account for specimen orientation is provided by MTEB 5-2 as follows:
i Reduce upper shelf Charpy energy values from longitudinal specimens to 65% of their value to estimate transverse values.
\ . .
TE WE ENGNEERING S8WICES Technical Report TR-6052-1, Rev. 1 2.2.1 Beltline The fracture toughness requirements of Appendix G, 10CFR50 (IV.A.1) specify minimum Charpy upper shelf energy levels for the beltline region of the reactor vessel. Initial upper shelf energy based on Charpy impact tests must be no less than 75 ft-lbs and must be maintained at no less than 50 ft-lbs throughout the vessel life. The initial upper shelf energy levels for the beltline material are reported by swr in Reference 6. Also reported is the decrease in shelf energy due to irradiation based on capsule specimen impact tests. This data along with the orientation adjustment is summarized below. Shelf Energy (ft-lbs) Initial Initial Longit. Transv. Shift 32 EFPY Base Metal 130 85* 15% 72 Weld Metal 113 113 27 82 HAZ 110 110 14 95 2.2.2 Closure Region, Shroud Region, F-N Nozzle Applying the MTEB 5-2 adjustment to the C-E upper shelf energy data gives: Shelf Energy (ft-lbs) Longit. Transv. 124 81 Head , 127 83
._ 9
f - TME ENGSEERING SERVICES Technical Report TR-6052-1, Rev. 1 (Cont'd) Shelf Energy (ft-lbs) longit. Transv. 123 80 Lower Shell , 130 85 115 75 147 96 F-W Nozzle > 148 96 136 88 130 85 Upper Shell > 123 80 135 88 3.0 OPERATIONAL LIMITS The pressure-temperature relationships tabulated below are determined using the results of TR-2318 adjusted for the impact properties determined in Section 2.0 and for irradiation, where applicable. 3.1 Closure Region T-RT Pressure I NDT T Ref. 2 Condition (psi) (KSI/Tn~) (F) $ Para. B
) , S.U./S.D. 0 (pr ad) 48.2 37 27 C.1.1 Head S.U./S.D. 250 68.7 83 73 C.1.1 RTNOT = -10F ) S.U./S.D. 500 94.9 117 108 C.1.1 S.U./S.D. 750 120.9 139 129 C.1.1 f d S.U./S.D. 1000 149.2 157 147 C.1.1
t
*TaEME ENGSEERNG SEMCES Technical Report TR-6052-1, Rev. 1 i (Cont'd) Kg T-RT Pressure NDT T Ref. 2 Condition (psi) (KSI/fn) (F) Q Para.
0 41.2 10 0 Pressure 750 88.7 110 100 C.1.2
- Tests 1000 109.2 130 120 C.1.2 1140 119.2 138 128 C.1.2 B
S.U./S.D. 0(pr ad) 125.5 142 137 C.1.1 Upper Shell S.U./S.D. 250 131.6 146 141 C.1.1 l S.U./S.D. 500 164.7 165 160 C.1.1 RTNDT = -5F S.U./S.D. 750 170.3 168 'o3 C.1.1 S.U /S.D. 1000 187.4 176 171 C.1.1 0 95 117 112 Pressure 750 104 125 120 C.1.2 Tests 1000 107.3 128 123 C.1.2 1140 109.2 130 125 C.1.2 When pressure exceeds 20% of the preservice system hydrostatic test pressure, Appendix G of 10CFR50 (IV.A.2) requires that the temperature of the closure flange regions, which are highly stressed by the bolt preload, exceed the RT NDT by: a) 120F for normal operation, and b) 90F for hydrostatic tests and leak tests. Twenty percent of preservice system hydrostatic pressure is 313 psi. Therefore: ) Minimum Closure Temperature (F) RT NDT II) Pressure (psi) Normal Operation Hydrotest Head -10 313 110 80 ) ffe{ -5 313 115 85 Theseconditionsaresatisfied(seeFigures4-1(a),(b),(c). I
L
*TaENNE
! ENGMERNG SERVICES Technical Report TR-6052-1, Rev. 1 f I ! 3.2 Shroud Suppett Reglon The beltline region is mere limiting than the lower shell with regard to both stress intensity factors and RTNOT. Therefore, the shroud support region need not be evaluated further. l i 3.3 Beltilne The operational limits for the beltline are determined herein l for various operational periods. N 3.3.1 End-0f-l.lfe At 32 EfPY the fluence and RT N3T shift at the 1/4 T location (weld metal) are predicted by swr (Refere,ce 6) to be 1.4 x 10 18 n/cm2 and 136F, respectively. Pressure I'! I"NI NDT Conditinn (psi) (KS! /I~n') (F) T (f) Ref. 2 Pago S.U./S.D. 1250 118.8 13/ 273 1050 100. 122 258 0-2-5 800 14.8 93 229 i $25 49. 40 116 B-2-5 400 37.4 -12 125 315 29.5 -105 31 } 263 24.4 -240 -104 B-2-5 Pressure 1250 89.3 110 246 Tests 1138 82.1 102 238 B-2-8 776 55.2 56 192 0-2-8 690 48.9 39 175 0-2 8 500 35.5 25 111 I 400 28.4 -141 -5 i I _ - _ -
l ! TME ENGMERIG SERVCES Technical Report TR-6052-1, Rev. 2 3.3.2 Intermediate Operational Periods The tabulations belows provide the predicted operational limits applicable to various operational periods between the current outage (6.68 EFPY) and about 1994 (14.3 EFPY). These are based on BECO projected fast neutron fluence on the Pilgrim RPV (Reference 7) and on the swr (Reference 6)predictedfluenceandRT NOT shift at the 1/4 T location l (weld metal) for the given operational period. (Note that the initial RT NDT for the beltline weld metal is 0F.) RPV Wall ART RT EFPY Fluence. 1/4 T NDT NOT 6.68 2.8 x 10 17 n/cm 2 61 61 8.0 3.4 x 10 17 n/cm 2 68 68 2 10.0 4.4 x 10 17 n/cm 76 76 12.0 5.1 x 10 I7 n/cm 2 82 82 14.3 6.1 x 10 17 n/cm 2 90 90 Subcritical lleatup/Cooldown Pressurtration Temperature f(F) T-RT
) Pressure NDT 14.3 FFPY I? FFPY 10 FFPY 8 EFPY 6.68 FFPY 1250 137 227 219 213 205 198 1050 122 212 204 198 190 183 800 93 183 175 169
) 525 40 161 154 l 130 122 116 108 101 1 400 - 12 78 70 64 56 49 315 -105 - 15 - 23 - 29 - 37 - 44 263 -240 -150 -158 -169 -172 -179
.)
l L
l WNNE ENGINEERING SERVICES Technical Report TR-6052-1, Rev. 1 I I i Hydro and Leak Tests Pressurization Temperature
.T(F)
T-RT 8 EFPY 6.68 EFPY Pressure NDT 14.3 EFPY 12 EFPY 10 EFPY 1250 110 200 192 186 178 171 1138 102 192 184 178 170 163 ) L 900 74 164 156 150 142 135 776 56 146 138 132 124 117 690~ 39 129 121 115 107 100 500 - 25 ~ 65 57 51 43 36 y 400- -141 - 51 - 59 - 65 - 73 - 80 A composite plot of the pressure-temperature relationship
") for the beltline region is shown in Appendix B, Figure B.1, for 8, 12 and 32 EFPY. I.; addition, Figure B.2 presents the results as a function of temperature above (or below) RT NDT*
3 A . Feedvater Nozzle
. The closure region is more limiting than the feedwater nozzle with regard to b'oth stress intensity factors and RTNDT. Therefore, the P-T y 1.iroits of the closure region will be controlling. At upper shelf tempera-tures the s' tress intensity f actor is 60.6 KSI/iii .
4.0 P_RFSSURE-TEMPERATURE LIMIT CUitVES Pressure-temperature limit curves are shown in Figures 4-1(a) through 4-1(c). Figure 4-1(a) reflects the predicted end-of-life (32EFPY) beltline RTNDT shift. Figures 4-1(b) and 4-1(c) represents the P-T limits
) for pressure tests and operating conditions, respectively. These curves represent the predicted conditions through about 1994 (14.3 EFPY). The following observations are noted: )
L
l TP WPE ENGNEERNG SERVICES Technical Report TR-6052-1, Rev. 1 h (1) The closure shell is limiting primarily due to the preload stress condition. (2) The indicated pressurizing temperature for the closure is always greater than the following: t Normal Operation: RTNDT + 120F = 115F
\ Pressure Tests: RTNDT + 90F = 85F This complies with 10CFR50, Appendix G, Pargaraph IV.A.2. )
(3) When the core is critical, the indicated pressurization temperature for the closure is greater than RTNDT + 60F = 55F. This complies with Paragraph IV.A.3. b (4) For the pressure tests of IV.A.4 the indicated pressurization temperature, T, complies with 10CFR50: RT EFPY T(F) NDT + 60F 8 170 128 12 184 142 32 238 196
)
5.0 REFERENCES
(1) 10CFR50, ApperJix G, Fracture Toughness Requirements, Effective
) July 26, 1933.
(2) Teledyne Engineering Services Technical Report TR-2318, Rev. 1, June 11, 1976 (Teledyne Materials Research).
)
(3) ASME BPVC, Section III, 1980 Edition and Addenda through Winter 1981.
)
_-_-__-___-------__A
WTF1 FTf(NE ENGNEERNG SERVICES Technical Report TR-6052-1, Rev. 2 ) (4) USNRC Standard Review Plan 5.3.2, " Pressure-Temperatere Limits," Rev. 1, July 1981 and MTEB 5-2. ) (5) Reactor Vessel Material Certification Test Results for Pilgrim 1, transmitted to BEC0 from C. E. Power Systems on May 11, 1976, Transmittal No. DRV-76-586. (6) Southwest Research Institute, Project Report 02-5951, "PNPS Reactor Vessel Irradiation Surveillance Program," July 1981. 3 (7) Boston Edison Co. Memorandum dated May 16,1984, " Projected f ast Neutron Fluence on Pilgrim Pressure Vessel," L. C. Hu to J. S. Roberts. 1 1
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WF RWNE ENGWEERING SERVICES Technical Report TR-6052-1, Rev. 1 ) f APPENDIX A s
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"RTELEDYNE Technical Report ENGINEERING SERVICES TR-6052-1, Rev. 1 -Al-APPENDIX A D Example Calculations
- 1) MTEB 5-2 Charpy V-Notch Adjustment for Specimen Orientation "If transverely-oriented Charpy V-notch specimens were not tested, the temperature at which 50 ft-lbs and 35 mils LE would have been obtained on tranverse specimens may be estimated by one of the following criteria.
- a. Test results from longitudinally-oriented -
specimens reduced to 65% of their value to provide conservative estimates of values expected from transversely oriented specimens.
- b. Temperatures at which 50 ft-lbs and 35 mils LE were obtained on longitudinally-oriented speci-mens increased 20F to provide a conservative estimate of the temperature that would have been required to obtain the same values on transversely-oriented specimens."
Figure A.1 shows the CE Charpy V-notch impact test results (Reference
- 5) for one longitudinal specimen of unirradiated beltline base material.
At 50 ft-lbs, the test temperature is 10F At 35 mils, the test temperature is -6F To apply the MTEB 5-2 (Reference 4) adjustment (a) for specimen orientation, enter the curves at:
- - - . .- . . - _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . __9
k WTF1 STh'NE ENGINEERING SERVICES Technical Report TR-6052-1, Rev. 1 -A2- - I
- Test Temperature = 48F h = 76.9 ft-lbs
- Test Temperature = 50F h=53.9 mils For adjustment (b) add 20F to the 50 ft-lbs/35 mils temperature values:
10 + 20 = 30F
-6 + 20 = 14F If these four temperature values are less than the dropweight TNDT plus 60F, then T is the reference temperature, RTNDT.
NDT In this example: DWTNDT = -30F A DWTNDT + 60 = +30F Thus, the above requirement is not met and the RT NDT is: 50F - 60 = -10F
- 2. MTEB 5-2 Estimation of T NDT fr m Charpy V-Notch Data when Dropweight Tests.-are not Available.
"If dropweight tests were not performed, but full Charpy V-notch curves were obtained, the NDTT for SA-533 Grade B, Class 1 plate and weld material may be assumed to be the temperature at which 30 ft-lbs was obtained in Charpy V-notch tests, or 0F, whichever was higher."
)
'#TF1 FrVNE ENGINEERING SERVCES Technical Report l TR-6052-1, Rev. 1 -A3-
) 4 Entering Figure 3 of Reference 6 at 30 ft-lbs gives a test temperature of -120F for unirradiated weld metal. Since OF is greater than this value TNDT = OF.
- 3. MTEB 5-2 Estimation of Upper-Shelf Energy from Longitudinal Specimens "If tests were only made on longitudinal specimens, the a
values should be reduced to 65% of the longitudinal values to estimate the transverse properties." From Figure 2 of Reference 6 the upper shelf energy is at least 1 130 ft-lbs. Therefore: 0.65 x 130 = 85 ft-lbs f
W TEl.EDYNE Technical Report ENGINEERING SERVK3ES l TR-6052-1, Rev. 1 -A4-
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