ML19263C526

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Reports Results of Sampling & Analysis Actions & Addl Operational Info for Four Periods When Reactor Thermal Power Changed by More than 15% of Rated Thermal Power within One Hour While in Operational Condition 1 or 2
ML19263C526
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 02/14/1979
From: Linder F
DAIRYLAND POWER COOPERATIVE
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
LAC-6114, NUDOCS 7902260435
Download: ML19263C526 (12)


Text

{{#Wiki_filter:. DAIRYLAND 1*0WEEE COUI*EftAY1VE Ba Grmw,01 human $4601 February 14, 1979 In reply, please refer to LAC-6114 DOCKET NO. 50-409 Mr. James G. Keppler Regional Director U. S. Nuclear Regulatory Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137

SUBJECT:

DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR) PROVISIONAL OPERATING LIGENSE NO. DPR-45 SPECIAL REPORT NO. 79-01

Reference:

(1) LACBWR Technical Specifications, Section 4.2.2.22, Action g. (2) LACBWR Technical Specifications, Section 3.9.4.1.

Dear Mr. Keppler:

In accordance with the provisions of Reference (1), a special report conforming to the requirements set forth in Reference (2) is submitted covering results of sampling and analysis actions together with additional operational information for four separate occasions when reactor thermal power changed by more than 15% of rated thermal power within one hour while in Operational Cor.dition 1 or 2. The separate occasions are discussed in Sections as follows: Section 1 - November 17, 1978 Section 2 - December 3, 1978 Section 3 - January 13, 1979 Section 4 - January 24, 1979 Each section provides a sunnary of operating data and radiological data for the time period prior to the thermal power change, along with the results of the additional sampling required. 79022604%f

Mr. James G. Keppler LAC-6114 Regional Director February 14, 1979 If there are any questions concerling the report, please contact us. Very truly yours, 7AIRYLAND POWER COOPERATIVE Frcak Linder, General Manager FL:LGP:af Attachment cc: Director, Office of Inspection and En.?orcement (30) U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Director, Office of Management Information and (3) Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Special Report No. 79-01 INTRODUCTION LACBWR Technical Specifications Section 4.2.2.22, Action g, requires sampling and analysis for Iodine-131, 133 and 135, as well as gross beta and gamma activity between 2 and 6 hours following a thermal power change of greater than 15% of rated thermal power within one hour. This special report is required to contain the information determined by the analysis plus additional information regarding reactor power history, fuel burnup, cleanup flow history, off-gas activity levels and gross alpha activity levels. Section 1 A reactor scram occurred from a power level of 62% at 2150 hours on November 17, 1978. A low flow spike indication of Forced Circulation Loop 1A caused indication of a power-to-flow mismatch in pover/ flow safety channel No. 1, which in turn initiated the reactor scram signal. Gross BY Activity and Iodine Analysis Time of Sample: 0018 Hours, November 18, 1978 Sample Results: Gross By: 1.10 pCi/ gram I l31 1.9581 x 10-2 pCi/ gram I l33 4.5498 x 10-2 pCi/ gram I 135 7.3787 x 10-2 pCi/ gram Additional Information 1. Reactor Thermal Power Level Starting 48 Hours Prior to the Thermal Power Change: 2100-2400 hrs., November 15, 1978: 54% 0000-0800 hrs., November 16, 1978: 54-55% 0800-1600 hrs., November 16, 1970: 55-57% 1600-2400 hrs., November 16, 1978: 57-59% 0000-0800 hrs., November 17, 1978: 59% 0800-1600 hrs., November 17, 1978: 59-60% 1600-2100 hrs., November 17, 1978: 60-62% 2. The Fuel Burnup of Assemblies in a Symmetrical Core Region is depicted in Figure 1. 3. Cleanup Flow History Starting 48 Hours Prior to the Thermal Power Change: Special Report No. 79-01 Primary Purification Flow Rate 2100 hrs., November 15, 1978 - 2100 hrs., Noveisber 17, 1978: 42-43 gpm Primary Purification Decontamination Factors (By) November 13, 1978: 166 November 16, 1978: 334 November 23, 1978: 79 4. Off-Gas Activity Levels (Ci/ day) for 48 Hours Prior to Thermal Power Change: 1600-2400 hrs., November 15, 1978: 342 Ci/d 0000-0800 hrs., November 16, 1978: 338 Ci/d 0800-1600 hrs., November 16, 1978: 375 Ci/d 1600-2400 hrs., November 16, 1978: 384 Ci/d 0000-0800 hrs., November 17, 1978: 447 Ci/d 0800-1600 hrs., November 17, 1978: 434 Ci/d 1600-2100 hrs., November 17, 1978: 378-415 Ci/d 5. Gross Alpha Activity Level Starting with the Last Sample Takun Prior to the Thermal Power Change: 0226 hrs., November 16, 1978: 4.5 x 10-7 pCi/ gram 2150 hrs., Novembar 17, 1978: Thermal Power Change 0249 hrs., November 21, 1978: 5.29 x 10-7 p Ci/ gram Section_2 An intentional reactor power reduction took place at 2232 hours on December 3, 1978, when indications of excessive wear of the upper face seal on Forced Circulation Pump 1A prompted securing of the pump. Reactor thermal power was reduced from 70% to 49%. Gross By Activity and Iodine Analysis Time of Sample: 0111 Hours, December 4, 1978 Sample Results: Gross By: 3.03 uCi/ gram I l31 8.73 x 10-3 uCi/ gram I l33 5.85 x 102 uCi/ gram I l35 1.14 x 101 uCi/ gram Special Report No. 79-01 Additional Information 1. Reactor Thermal Power Level Starting 48 Hours Prior to the Thermal Power Change: 2200-2400 hrs., December 1, 1978: 62-63% 0000-0800 hrs., December 2, 1978: 62-64% 0800-1600 hrs., December 2, 1978: 63-64% 1600-2400 hrs., December 2, 1978: 64-67% 0000-0800 hrs., December 3, 1978: 67-70% 0800-1600 hrs., December 3, 1978: 70? 1600-2232 hrs., December 3, 1978: 70% 2. The Fuel Burnup of Assenblies in a Symmetrical Core Region is Depicted in Figure 2. 3. Cleanup Flow History Starting 48 Hours Prior to the Thermal Power Change: Primary Purification System Flow Rates: 2100 hrs., December 1, 1978 - 2100 hrs., December 3, 1978: 42-42.5 gpm Primary Purification Decontamination Factors (8y) November 27, 1978: 154 December 4, 1978: 248 4. Off-Gas Activity Levels (Ci/ day) for 48 Hours Prior to Thermal Power Change: 2100-2400 hrs., December 1, 1978: 596 Ci/d 0000-0800 hrs., December 2, 1978: 598 Ci/d 0800-1600 hrs., December 2, 1978: 565 Ci/d 1600-24^0 hrs., December 2, 1978: 563 Ci/d 0000-085 hrs., December 3, 1978: 647 Ci/d 0800-1600 hrs., December 3, 1978: 665 Ci/d 1600-2400 hrs., December 3, 1978: 623 Ci/d 5. Grosc Alpha Activity Level Starting with the Last sample Taken Prior to the Thermal Power Change: 7 0442 hrs., Novencer 30, 1978: 3.11 x 10 uCi/ gram 2232 hrs., December 3, 1978: Thermal Power Ch.'nge 0111 hrs., December 4, 1978: 2.5 x 10-7 uCi/ gram Special Report No. 79-01 Section 3 A reactor scram occurred from a power level of 49% at 0835 hours on January 13, 1979. A short circuit to ground in a scram solenoid of a control rod drive caused the rod to scram. Low voltage on the non-interruptible bus, which was indirectly induced by the one rod scramming, initiated a full reactor scram. Gross By Activity and Iodine Analysis Time of Sample: 1140 Hours, January 13, 1979 Sample Results: Gross By: 1.223 uCi/ gram Il31 7.909 x 10-2 pCi/ gram I l33 1.142 x 10-1 uCi/ gram I l35 1.182 x 10-1 uCi/ gram Additionni Information 1. Reactor Thermal Power Level Starting 48 Hours Prior to the Thermal Power Change: 0800 hrs., January 11, 1979 - 0800 hrs., January 13, 1979: 49-50% 2. The Fuel Burnup of Assemblies in a Symmetrical Core Region is Depicted in Figure 3. 3. Cleanup Flow History Starting 48 Hours Prior to the Thermal Power Change: Primary Purification Flow Rate 0800 hrs., January 11, 1979 - 0800 hrs., January 13, 1979: 40 gpm Primary Purification Decontamination Factors (8Y) January 11, 1979: 153 January 16, 1979: 124 4. Off-Gas Activity Levels (Ci/ day) for 48 Hours Prior to Thermal Power Change: 0800-1600 hrs., January 11, 1979: 312 Ci/d 1600-2400 hrs., January 11, 1979: 302 Ci/d 0000-0800 hrs., January 12, 1979: 288 Ci/d 0600-1600 hrs., January 12, 1979: 338 Ci/d 1600-2400 hrs., January 12, 1979: 298 Ci/d 0000-0800 hrs., January 13, 1979: 283 Ci/d 4-

Special Report No. 79-01 5. Gross Alpha Activity Level Starting with the Last Sample Taken Prior to the Thermal Power Change: 0116 hrs., January 11, 1979: 9.61 x 10-7 pCi/ gram 0835 hrs., January 13, 1979: Thermal Power Change 0043 hrs., January 16, 1979: 9.70 x 10-7 pCi/ gram Section 4 A reactor partial scram occurred from a power level of 31% at 2042 hcurs on January 24, 1979. The partial scram was initiated by a low control rod drive accumulator oil level condition. The remaining control rods were manually scrammed. Gross By Activity and Iodine Analysis Time of Sample: 0105 Hours, January 25, 1979 Sample Results: Gross By: 0.267 pCi/ gram I l31 7.706 x 10-3 pCi/ gram I l33 1.250 x 10-2 pCi/ gram I 135 2.082 x 10-2 pCi/ gram Additional Information 1. Reactor Thermal Power Level Startup 48 Mours Prior to the Thermal Power Change: 2000 hrs., January 22, 1979 - 0800 hrs., January 23, 1979: < 1% 0800-1600 hrs., January 23, 1979: < 1% - 23% 1600-2000 hrs., January 24, 1979: 23-32% 2. The Fuel Burnup of Assemblies in a Symmetrical Core Region is Depicted in Figure 4. 3. Cleanup Flow History Starting 48 Hours Prior to the Thermal Power Change: Primary Purification Flow Rates 2000-2100 hrs., January 22, 1979: 41 gpm 2100 hrs., January 22, 1979 - 0600 hrs., January 23, 1979: System Shut Down 0600 hrs., January 23, 1979 - 2000 hrs., January 24, 1979: 42.5 gpm Primary Purification Decontamination Factors (8v) January 19, 1979: 105 January 25, 1979: 145 Special Report No. 79-01 4. Off-Gas Activity Levels (Ci/ day) for 48 Hours Prior to Thermal Power Change: 2000 hrs., January 22, 1979 - 0600 hrs., January 24, 1979: <1 Ci/d 0600-0800 hrs., January 24, 1979: 1-3 Ci/d 0800-1600 hrs., January 24, 1979: 3-107 Ci/d 1600-2000 hrs., January 24, 1979: 107-119 C1/d 5. Gross Alpha Activity Level Starting with the Last Sample Taken Prior to thc ' ermal Power Change: 0043 hrs., January 16, 1979: 9.70 x 10-7 pCi/ gram 2042 hrs., January 24, 1979: Thermal Power Change 0050 hrs., January 29, 1979: 5.72 x 10-7 uCi/ gram Quarter Core Fuel Exposure Estimation (GWD/MTU) as an Indication of Regional Exposure as of November 17, 1978. ' Core Average Exposure N 8.694 GWD/MTU. A B C D E F G H K L l t =:Ra =i 2 y 'l_i_Y_ q ~.__2_~j [7__1.,',/C_11_L.____ill/GMTi.@_lTf_.~/7_3 ~ I4 (_ 3 U_g i I k ._J i _ q _ L ag;___,J _ JJc;;;g:n@t}J _ ___ _ J e;;n 4 j d--,. d =_- = b t ao. I= = L==1 L= __'r Lpf;.Rlq _ _1 n y _ _ g!r =sRJ ln! i 5 1, y _ g gjt j jj F,!i iLC:pKa _ H'uxDOEZ i;Za _ Eq9;;al@_t= q?ria 6 I

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