ML20126E560

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Special Rept 26:Cycle 15 Startup Rept
ML20126E560
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 01/16/1978
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20126E558 List:
References
NUDOCS 8102050303
Download: ML20126E560 (23)
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{{#Wiki_filter:* (m) x/ CONSIES PC'JER C0!?A!TY 3IG ROCK PCI C PLWT Specihl Report No 26 CYCLE 15 START-UP EZPCRT Prepared by: Consumers Power CO pany Janua.f 16, 1978 {D

A. INTRODUCTION The 15th cycle at Big Rock Point was designed for operation between 210 and 230 MWt over a period of approximately 11 months. Included in the core load-ing are the following Big Rock Point fuel designs: Number of Fuel Tree Assemblies General Electric Reload F 20 ExKon Nuclear Reload G 28 Exxon Nuclear Reload G - 1U 20 Exxon Nuclear Reload G - 3 16 Each of the Reload G are mixed-oxide assemblies. Of the 22 fresh assemblies loaded into the core,16 vere of the Reload G - 3 design which is being uti-lized at Big Rock Point for the first time. B. EXPERIMENTS Modifications were made to lh fuel assemblies during the lhth refueling outage for research and development purposes. These experiments include: Exteriment Modified Assembly 1. Exxon Cladding G-01, G-21 Ductility Program 2. General Electric F56, F57, F60, F61, Corner Rod Program F62, F63, F6L, F65, FT1, F76, F81 FS3 The following is a brief description of these modifications: 1. Exxon Cladding Ductility Program Two fuel rods from Assembly G-01 and three fuel rods from assembly G-20 were removed and replaced with inert circalloy rods. The removal of the fueled rods is a part of an Exxon /EPRI program to produce high ductility cladding and is an extension of the program originally de-scribed by letter to the Directorate of Licensing dated July 9,197L. ) In each case, the reactivity change associated with the removal of the fuel rods was less than.2% Ak/k. Minor peaking increases occurred in the vicinity of the replacement inert rods (on the order of several percent) and thermal hydraulic analyses have been adjusted appropriately to account for this change. The rods removed from the assemblies are to be sent off site for destructive examination. ) 1

2. General Electric Corner Rod Program Twelve Reload F assemblies were returned to the core for Cycle 15 with GE corner rod experiments in the corner locations which normally contain cobalt (h8 rods total). The GE corner rod program (described by letter to the Directorate of Licensing dated March 26,197h) was expanded to include eight relatively high cross-section rods containing Inconel cou-pons. The replacement of the original low cross-section specimens with Inconel ensures that the reactivity of the modified fuel assemblies is typical of those osse =blies still containing cobalt in the corner loca-tions. To obtain the effects of full reactor environment on these speci-ments, four of the rods have holes allowing reactor coolant contact with the coupons. C. TECHNICAL SPECIFICATION TESTING On completion of core reconstitution, core shutdown margin verification was performed in accordance with Technical Specification 5 2.2(b). Computer cal-culations indicated a total shutdown margin in excess of 2 9% Ak/k with the highest worth blade (approximately 3 9% ak/k) withdrawn from the core. This is well in excess of the.3% Ak/k Technical Specification shutdown margin requirement. The Cycle 13 BOL cold critical control rod pattern was in agreement with the predicted pattern and is presented in Figure 1. A moderator temperature coefficient test was performed to ensure conformance with Technical Specifications Section 5 2.h. Results of the test indicated a maximum addition of reactivity of 9 3d from ambient (approximately TO F) to approximately 100 F, well within the Technical Specification limitation of one dollar. This was in very good agreement with computer predictions. Figures 2 and 3 are plots of p and the temperature coefficient (ao/aT), each as a function of temperature. D. START-UP Initial power escalation was very slow, occurring over a four-week period. This relatively slow rate of start-up was a result of the fuel preconditioning requirements. On attaining a power level of approxinately 195 MWt, control rod drive Bh failed to respond to withdrawal signals (R0 No TT h6 dated December 9, 1977). Repeated attempts to withdraw the rod eventually resulted in the rod being placed in the full-in position. As a result, current power operation is restricted to 205 MWt, approximately 20 MWt less than achievable with the drive at its intended position. Repair of the drive and subsequent return to normal power operation is expested in January 1978. Flux profiles for each of the eight in-core monitor locations were obtained at a power level of 205 MWt. Figures b through 12 are comparisons of these profiles with computer predictions. With the exception of the problems encountered with control rod drive BL, the start-up was uneventful. All predicted and measured parameters were in good agreement and sll well within Technical Specification limits. 2

FIGURE 1 CRITICAL CONTROL R0D PATTERN (Rod Positions Shown in Notches Withdrawn) 4 A' B C D E F 1 5 5 4 5 2 5 0 .0 0 0 5 1 3 4 0 0 0 0 5 4 5 0 0 0 0 4 s 5 0 0 0 0 5 e 5 4 5 4 PREDICTED CRITICAL PATTERN Total Notches Withdrawn = 81 A B C D E F 1 5 5 4 5 2 5 0 0 0 0 5 3 4 0 0 0 0 5 4 5 0 0 0 0 4 s 4 0 0 0 0 5 6 5 4 5 5 ACTUAL CRITICAL PATTERN t ^< 400 SECONDS TEMP = 100*F Total Notches Withdrawn = 81 ' f. .,w... m .c-..

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i o I FIGURE 2 CYCLE 15 H0DERATOR j TEMPERATURE 1 COEFFICIENT TEST p VS TEMP t k i i 1 8.0 - e 4 7.0 - ~ i 6.0 - O f Of j s.0 / N / g COMPUTER PREDICTION / N .L 0 3.0 / N y MEASURED N / N 2.0 - / 10 / 1 1 1 I I I I f 70 0 0 100 110 120 130 14 0 TEMPERATURE *F -.. ~

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RFGULATORY INFORMATION DISTRIBUTION SYSTFM (RID.) DICTRIBUTION FnR INCOMING MATERIAL 50-155 REC: KFPPlFR .I P ORG: ST:I BI T %:Y N 5 DOCDATE: 01/16/78 NRC CONSUMERS P!,tR DATF ' PCVD: 01/19./76 DOCTYPE:

1. F l TFE NOTARI7FO: NO COPIES RECEIVED

SUBJECT:

LTR O ENCL 2 F ORWARDING SPEC I AL REPT NO 26 FNTITLED " CYCLE 15 START-UP REPT" TO FULFILL REOUIREMENTS OF TECH SPEC SECTION 6.9.1(A). I'L ANT NANF F:.T r4 FOCf: F1 REVIEWFP INIrisL:

  • JM DISIHJBUTOR IN11IAL o o u * *o* *+w *
  • DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS *******n**** **o GFNFRAL DIiTRIBUTION FOR AFTER Ic:SUANCE OF OPERATING LICENSE.

FOR ACTION. ERANCH CHIEF DAVIS * *LU7 ENC! INTFRNAL 3F Ee l-NRC PDR**W/ ENCL 1 ~ FYtt? - 9 -rn. OELD4-*L1 R ONLY HANAUFR**W/ENCI CHECK **W/ ENCL E I 9ENHUT++ W/FNCl. SHAO**W/FNCl. BAER**W/ ENCL. BUTLFH**W/ ENCL GRIMES **W/FNCL J. COLL.I NS++W/FtK L J. MCOOUGH nW/F.lEL E:< TERN A!. LPDR'S C HARI FVOX., MI++W/FHCL T I C *<>W/FHCl. NSIC++W/Flfl ACRS C AT E+d W/16 ENCL l ) / / DISTRIBUTION: LTR 40 FNCl. 39 CONTROL NBR: 780190018 SIZE: 1P+2SP

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THE END

                        • ++**+*+****++++****'

/ s consumers ( Pov:cr EEH03Y D:BIET P.'.5 00f'Y Company m. (( + General Offices: 212 West Michigan Avenue,Jeckson, Michigan 49201 e Area Code 517788-0550 January 16, 1978 l O-.,"{(f,, ,/ /. k:\\ 0' j gN A vy Jn U w

91 %

Mr James G Keppler 8 4 ;- Office of Inspection and Enforcement g' g%, %, j/ Region III US Nuclear Regulatory Commission gro p-T99 Roosevelt Road tu Glen Ellyn, IL 60137 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLAUT - SPECIAL REPORT NO 26: CYCLE 15 START-UP PIPORT Transmitted attached is Special Report No 26 for the Big Rock Point Plant. This report is entitled, " Cycle 15 Start-Up Report" and is submitted to fulfill the requirenents of Technical Specifications Section 6.91(a). W S Skibitsky (Signed) W S Skibitsky Nuclear Licensing Engineer CC: DKDavis, USNRC 780190018 k [ 00I k o /z 1 s

i l i ) CONSIFIRS POWER COMPANY BIG ROCK POIITI PLAllT Special Report No 26 CYCLE 15 START-UP REPORT Prepared by: Consu=ers Power Company January 16, 1978 f y w

i l A. INTRODUCTION The 15th cycle at Big Rock Point was designed for operation between 210 and 230 MWt over a period of approximately 11 months. Included in the core load-ing are the following Big Rock Point fuel designs: Number of Fuel Type Assemblies General Electric Reload F 20 Exxon Nuclear Reload G 28 Exxon Nuclear Reload G - 1U 20 Exxon Nuclear Reload G - 3 16 Each of the Reload G are mixed-oxide assemblies. Of the 22 fresh assemblies loaded into the core, 16 were of the Reload G - 3 design which is being uti-lized at Big Rock Point for the first time. B. EXPERIMENTS Modifications were made to 14 fuel assemblies during the lhth refueling outage for research and development purposes. These experiments include: Experiment Modified Assembly 1. Exxon Cladding G-01, G-21 Ductility Program 2. General Electric F56, F57, F60, F61, Corner Rod Program F62, F63, F6h, F65. FT1, FT6, F81, F83 The following is a brief description of these modifications: 1. Exxon Cladding Ductility Program Two fuel rods from Assembly G-01 and three fuel rods from assembly G-20 were removed and replaced with inert zircalloy rods. The removal of the fueled rods is a part of an Exxon /EPRI program to produce high ductility cladding and is an extension of the program originally de-scribed by letter to the Directorate' of Licensing dated July 9,1974 In each case, the reactivity change associated with the removal of the fuel rods was less than.2% ak/k. Minor peaking increases occurred in the vicinity of the replacement inert rods (on the order of several percent) and thermal hydraulic analyses have been adjusted appropriately to account for this change. The rods removed from the assemblies are to be sent off site for destructive examination. j j i 1

2. General Electric Corner Rod Program Twelve Reload F assemblies were returned to the core for Cycle 15 with GE corner rod experiments in the corner locations which normally contain cobalt (h8 rods total). The GE corner rod program (described by letter to the Directorate of Licensing dated March 26,197h) was expanded to include eight relatively high cross-section rods containing Inconel cou-pens. The replacement of the original low cross-section specimens with Inconel ensures that the reactivity of the modified fuel assemblies is typical of those assemblies still containing cobalt in the corner loca-tions. To obtain the effects of full reactor environment on these speci-ments, four of the rods have holes allowing reactor coolant contact with the coupons. C. TECHNICAL SPECIFICATION TESTING On completion of core reconstitution, core shutdown margin verification was performed in accordance with Technical Specification 5.2.2(b). Computer cal-culations indicated a total shutdown margin in excess of 2 9% Ak/k with the highest worth blade (approximately 3 9% Ak/k) withdrawn from the core. This is well in excess of the.3% ak/k Technical Specification shutdown margin requirement. The Cycle 13 BOL cold critical control rod pattern was in agreement with the predicted pattern and is presented in Figure 1. A moderator temperature coefficient test was performed to ensure conformance with Technical Specifications Section 5 2.h. Results of tne test indicated a maximum addition of reactivity of 9 3d from ambient (approximately TO F) to approximately 100 F, well within the Technical Specification limitation of one dollar. This was in very good agreement with computer predictions. Figures 2 and 3 are plots of p and the temperature coefficient ( Ap/6T), each as a function of temperature. D. START-UP Initial power escLlation was very slow, occurring over a four-week period. This relatively slow rate of start-up was a result of the fuel preconditioning requirenents. On attaining a, power level of approximately 195 MWt, control rod drive Bh failed to respond to withdrawal signals (R0 No 77 h6 dated December 9, 1977). Repeated attempts to withdraw the rod eventually resulted in the rod being placed in the full-in position. As a result, current pcVer operation is restricted to 205 MWt, approximately 20 MWt less than achievable with the drive at its intended position. Repair of the drive and subsequent return to normal power operation is expected in January 1978. Flux profiles for each of the eight in-core monitor locations were obtained at a power level of 205 MWt. Figures h through 12 are comparisons of these profiles with computer predictions. With the exceptien of the problems encountered with control rod drive BL, the start-up vas uneventful. All predicted and measured parameters were in good agreement and all vell within Technical Specification limits. 2

.~. _ f FIGURE 1 CRITICAL CONTROL ROD PATTERN (Rod Positions Shown in Notches Withdrawn) t h A B C D' E F 1 5 5 4 5 2 5 0 0 0 0 5 3 4 0 0 0 0 5 4 5 0 0 0 0 4 s 5 0 0 0 0 5 e 5 4 5 4 T' PREDICTED CRITICAL PATTERN Total Notches Wi thdrawn = 81 f A B C D E F 1 5 5 4 5 2 5 0 0 0 0 5 3 4 0 0 0 0 5 4 5 0 0 0 0 4 s 4 0 0 0 0 5 e 5 4 5 5 ACTUAL CRITICAL PATTERN i T s 400 SECONDS TEP.P = 100'F Total Notches Withdrawn = 81 f .,~.,..,...,,7 ,,,,,.-,..,,m,..y ,...e,, ,,,,.y...,-v.,

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