Text

Forwards Special Rept 78-02 on Results of Sampling & Analysis W/Addl Operating Info for Five Occasions When Reactor Thermal Power Changed More than 15% of Rated Thermal Power within 1 H While in Operating Conditions 1 or 2
	ML20062A684
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	09/26/1978
From:	Madgett J; DAIRYLAND POWER COOPERATIVE
To:	James Keppler; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
	TASK-03-06, TASK-05-06, TASK-3-6, TASK-5-6, TASK-RR LAC-5479, NUDOCS 7810170183
	Download: ML20062A684 (15)
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A D.1IR)Lt.%D POWER COGI*ER.tTAVE Ba Soua, Oncons 54601 September 26, 1978 In reply, please refer to LAC-5479 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 LICENSE NO. DPR-45 SPECIAL REPORT NO. 78-02

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 five separate occasions when reactor thermal power changed by more than 15% of rated thermal power within one hour while in Operational Condition 1 or 2.

The separate occasions are discussed in Sections as follows:

Section 1 - July 1, 1978 Section 2 - August 15. 1978 Section 3 - August 17, 1978 Sectien 4 - August 19, 1978 Section 5 - August 24, 1978 Each section provides a summary 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.

7 Er/ 0 / 7 0/E3 f ~! C 1978

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Mr. James G. Keppler, Regional Director LAC-5479 U. S. Nuclear Regulatory Commission September 26, 1978 If there are any questions concerning the report, please contact us.

Very truly yours, DAIRYLAND POWER COOPERATIVE 0

'Y John P. Madgett, General Manager JPM:LGP:af Attachment Director, Office of Inspection and Enforcement (30) cc-U. S. Nuclear Regulatory Commissien Washington, D. C.

20555 Director, Office of Management Information and (3)

Program Control U. S. Nuclear Regulatory Commission Washington, D. C.

20555....

-~_

S.'ECI AL REPORT 78-02 i

SECTION 1 l

A reactor scram occurred from a power level of 84% at 1530 hours0.0177 days 0.425 hours 0.00253 weeks 5.82165e-4 months on July 1,1978.

j The scram was caused by a spurious neutron flux spike indication which was received on nuclear instrument channel No. 8 which, in turn, caused an indication of a power-to-flow mismatch in power-flow safety channel No. 2.

The P/F safety channel operates on a 1 of 2 scram logic.

LACBWR Technical Specifications Section 4.2.2.22, Action g, requires an additional sampling for Iodine 131, fodine 133 and Iodine 135, as well as specific activity between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months af ter the completion of a thermal power change of greater than 15% of rated thermal power within one hour. The Special Report is required to contain the information determined by this additional analysis plus Additional Information as outlined below.

Time of additional sample:

2010 hours0.0233 days 0.558 hours 0.00332 weeks 7.64805e-4 months on July 1, 1978 j

Sample results: Gross 8 :

2.2J p Ci/ gram II3 2.01 x 10-2 p Ci/ gram j

Il33:

8.83 x 10-2 y Ci/ gram I135:

5.94 x 10-2 p Ci/ gram ADDITIONAL INFORMATION 4

s 1.

Reactor power level starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the thermal power change:

0800-1600 hrs. June 29, 1978:

84.0%

1600-2400 hrs. June 29, 1978:

84.4%

0000-0800 hrs. June 30, 1978:

84.3%

0800-1600 hrs. June 30, 1978:

84.1%

1600-2400 hrs. June 30, 1978:

84.0%

0000-0800 hrs. July 1, 1978:

84.3%

0800-1530 hrs. July 1, 1978:

84.1%

i 1

2.

The fuel burnup for assemblies in a symmetrical core region is depicted in j

Figure 1.

1 3.

Cleanup flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the thermal power change:

Primary Purification Flow Rate 0800 hrs., June 29, 1978 to 1600 hrs., July 1, 1978:

40.0 gpm Primarv Purification Decen unination Factors (BY)

June 28, 1971..

777 July 3, 1978:

817 I

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SPECIAL REPORT 78-02 SECTION 1 - (Cont'd) 4.

Offgas levels for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the thermal power change:

0800-1600 hrs., June 29, 1978:

539 Ci/d 1600-2400 hrs., June 29, 1978:

467 Ci/d 0000-0800 hrs., June 30, 1978:

503 Ci/d 0800-1600 hrs., June 30, 1978:

645 Ci/d 1600-2400 hrs., June 30, 1978: 516 Ci/d 0000-0800 hrs., July 1, 1978:

509 Ci/d 0800-1530 hrs., July 1, 1978:

498 Ci/d 5.

Gross alpha activity levels for the periods 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months before and af ter the thermal power change:

0230 hrs., June 29, 1978:

5.28 x 10-7 9 Ci/ gram 1530 hrs., July 1, 1978:

THEFF.AL PCf4ER CHANGE 0306 hrs., July 3, 1978:

2.90 x 10-6 9 Ci/ gram 0128 hrs., July 10, 1978:

6.68 x 10-7 u Ci/ gram SECTION 2 A reactor scram occurred from a power level of 81% at 1011 hours0.0117 days 0.281 hours 0.00167 weeks 3.846855e-4 months on August 15, 1978. The scram was caused by a spurious neutron flux spike indication which was received en nuclear instrument channel No. 8 which, in turn, caused an indication of a power-flow mismatch in power-flow safety channel No. 2.

The P/F safety channel operates on a 1 of 2 scram logic.

LACBWR Technical Specifications Section 4.2.2.22, Action g, requires an additional sampling for Iodine 131, Iodine 133 and Iodine 135, as well as specific activity between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months af ter the completion of a thermal power change of greater than 15% of rated thermal power within one hour. The Special Report is required to contain the information determined by this additional analysis plus Additional Information as outlined below.

Time of additional sample:

1300 hrs. on August 15, 1978~

Sample results: Gross Sy:

1.87 p Ci/ gram II31:

2.01 x 10-2 p Ci/ gram II33:

4.49 x 10-2 y Ci/ gram Il35:

5.23 x 10-2 u Ci/ gram l

l ADDITIONAL INFORMATION 1.

Reactor power level starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the thermal power change:

i 0S00-1600 hrs., Aug ast 13, 1978; 81.0%

}

1600-2400 hrs., August 13, 1978:

80.9%

0000-0800 hrs., August 14, 1978:

80.8%

0800-1600 hrs., August 14, 1978:

80.6%

1600-2400 hrs., August 14, 1978:

80.5%

0000-0800 hrs., August 15, 1978:

80.1%

0800-1011 hrs., August 15, 1978:

80.0%

SPECIAL REPORT 78-02 SECTICN 2 - (Cont'd) 2 The fuel burnup for assemblies in a syLxttrical core region is depicted in Figure 2.

3.

Cleanup flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the thermal power change:

Primary Purification Flow Rate 0800 hrs., August 13, 1978 to 1100 hrs., August 15, 1978:

40 gpm Primary Purification Decontamination Factors (BY)

August 10, 1978:

494 August 14, 1978:

776 August 17, 1978:

1,052 4.

Offgas levels for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the thermal power change 0800-1600 hrs., August 13, 1978:

476 Ci/d 1600-2400 hrs., August 13, 1978:

495 Ci/d 0000-0800 hrs., August 14, 1978:

463 Ci/d 0800-1600 hrs., August 14, 1978:

463 Ci/d 1600-2400 hrs., August 14, 1978:

476 Ci/d 0000-0800 hrs., August 15, 1978:

468 Ci/d 0800-1011 hrs., August 15, 1978:

468 Ci/d 5.

Gross alpha activity levels for the periods 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months befcre and af ter the thermal power change:

0240 hrs., August 10, 1978:

4.41 x 10-7 u Ci/ gram 0104 hrs., August 14, 1978:

5.13 x 10-7 u Ci/ gram 1011 hrs., August 15, 1978: THERMAL POWER CHANGE 0416 hrs., August 17, 1978:

6.44 x 10-7 u Ci/ gram 0110 hrs., August 21, 1978:

6.44 x 10-7 u Ci/ gram SECTICN 3 At 0418 hours0.00484 days 0.116 hours 6.911376e-4 weeks 1.59049e-4 months on August 17, 1978, a manual reactor shutdown was initiated to repair the turbine bypass valve actuator which was leaking hydraulic fluid. The reactor was shut down with all rods inserted at C623 hours. Prior to shutdown, the reactor had been operating at 33% of rated thermal power.

LACEWR Technical Specifications Section 4.2.2.22, Action g, requires an additional sampling for Iodine 131, Iodine 133 and Iodine 135, as well as specific activity between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months af ter the completion of a daermal power change of greater than 15% of rated thermal power within one hour. The Special Report is required to contain the information determined by this additional analysis plus Additional Information as outlined below.. -.

m SPECIAL REPORT 78-02 i

SECTION 3 - (Cont'd) a Time of additional sample: 1025 hrs. on August 17, 1978 Sample results: Gross S :

1.01 p Ci/ gram II3 4.27 x 10-2 y Ci/ gram i

II33:

1.37 x 10-2 9 Ci/ gram I135:

1.28 x 10-2 9 Ci/ gram ADDITIONAL INFORMATION I

1.

Reactor power level starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the thermal power. change 0000-0800 hrs., August 15, 1978:

80.1%

0800-1011 hrs., August 15, 1978:

80s 1011-1600 hrs.,. Augus t 15, 1978:

On 1600-2400 hrs., August 15, 1978:

0%

0000-0000 hrs., August 16, 1978:

0%

)

0800-1600 hrs., August 16, 1978:

0% (Reactor startup) i.

1600-2400 hrs., August 16, 1978:

0% + 204 (Power escalation) 0000-0418 hrs., August 17, 1978:

20% + 33% (Power escalation) 0418-0623 hrs., August 17, 1978:

33% + 0% (Reactor shutdown) 2.

The fuel burnup for assemblies in a symmetrical core region is depicted in Figure 3.

3.

Cleanup flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the thermal power change Primary Purification Flow Rate l

0000 hrs. - 1100 hrs., August 15, 1978:

40 gpm j-1100 hrs., August 15, 1978 - 1500 hrs., August 16, 1978:

System Shutdown 1500 hrs., August 16, 1978 - 0700 hrs., August 17, 1978:

40 gpm Primary Purification Decontamination Factors (6Y)

August 14, 1978:

776 August 17, 1978:

1,052 August 20, 1978:

726 4.

Of # gas levels for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the thermal power change:

0000-0800 hrs., August 15, 1978:

468 Ci/d 0800-1011 hrs., August 15, 1978:

468 Ci/d 1011-1600 hrs., August 15, 1978: System Shutdown 1600-2400 hrs., August 15, 1978: System Shutdown 0000-C800 hrs., August 16, 1978: System Shutdown 0800-1600 hrs., August 16, 1978: System Shutdown 1600-2400 hrs., August 16, 1978:

84 Ci/d @ 20s Power 0000-0418 hrs., August 17, 1978:

228'Ci/d 9 33% Power 0500 hrs., August 17, 1978: 85 Ci/d De-escalating Power 0600 hrs., August 17, 1978: 23 Ci/d De-escalating Power. - -

i SPECIAL REPORT 78-02 SECTIOtt 3 - (Cont'd) 5.

Gross alpha activity levels for the periods 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months before and af ter the thermal power change:

0104 hrs., August 14, 1978:

5.13 x 10-7 p Ci/ gram 0416 hrs., August 17, 1978:

6.44 x 10-7 p Ci/ gram 0418 hrs., August 17, 1978:

"HERMAL PCWER CHANGE 0110 hrs., Aujust 21, 1978:

6.44 x 10-7.p Ci/ gram SECTION 4 Reactor power escalation was in effect when, at 0829 hours0.00959 days 0.23 hours 0.00137 weeks 3.154345e-4 months , on August 19, 1978, a reactor scram occurred from a power level of 62%.

A malfunctioning electrical-to-pneumatic control relay on a seal injection differential pressure control valve caused the forced circulation pumps to trip on a low seal injection flow signal which, in turn, resulted in a reactor scram.

LACBWR Technical Specifications Section 4.2.2.22, Action g, requires an additional smnpling for Iodine 131, Iodine 133 and Iodine 135, as well as specific activity between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months af ter the completion of a thermal power change of greater than 15% of rated thermal power within one hour. The Special Report is required to contain the information determined by this additional analysis plus Additional Information as outlined below.

Time of additional sample:

1106 hrs., August 19, 1978 Sample results: Gross By:

1.11 p Ci/ gram I l31:

4.97 x 10-3 p Ci/ gram Il33:

7.21 x 10-3 p Ci/ gram I t35:

8.45 x 10-3 p Ci/ gram ADDITIONAL INFORMATION 1.

Reactor power level starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the thermal power change:

0800-1035 hrs., August 17, 1978: 0%

1035-1600 hrs., August 17, 1978: 0% to 0.6% Reactor Startup 1600-2400 hrs., August 17, 1978:

0.6% to 26% Power Escalation l

0000-0800 hrs., August 18, 1978:

26% to 41% Power Escalation 0800-1600 hrs., August 18, 1978:

41% to 51% Power Escalation 1600-2400 hrs., August 18, 1978:

51% to 57% Power Escalation 0000-0800 hrs., August ~19, 1978:

57% to 62% Power Escalation 0800-0829 hrs., August 19, 1978: 62%

2.

The fuel burnup for assemblies in a symmetrical core region is depicted in Figure 4.

3.

Cleanup flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the thermal power change: !

~

SPECIAL REPORT 78-03 i

l SECTION 4 - (Cont'd)

Primary Purification Flow Rate" 0700-1500 hrs., August 17, 1978: System Shutdown 1500 hrs., August 17, 1978 - 1600 hrs., August 18, 1978:

40 gpm 1600 hrs., August 18, 1978 - 2300 hrs., August 19, 1978:

System Shutdown Primary Purification Decontamination Factors (BY)

August 17, 1978:

1,052 August 20, 1978:

726 4.

Offgas level for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the thermal power change:

0800-1600 hrs., August 17, 1978: System Shutdown 1600-2400 hrs., August 17, 1978:

101 Ci/d @ % 26% Power 0000-0800 hrs., August 18, 1978:

225 Ci/d 9 % 41% Power 0800-1600 hrs., August 18, 1978:

360 Ci/d @ N 51% Power 1600-2400 hrs., August 18, 1978: 497 Ci/d 9 % 57% Power 0000-0800 hrs., August 19, 1978: 446 Ci/d 3 % 62% Power 0800-0829 hrs., August 19, 1978:

446 Ci/d 9 % 62% Power 5.

Gross alpha activity levels for tne periods 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months before and af ter the thermal power change:

0416 hrs., August 17, 1978:

6.44 x 10-7 p Ci/ gram 0829 hrs., August 19, 1978: THEPMAL POWER CHANGE 0110 hrs., August 21, 1978:

6.44 x 10-7 u Ci/ gram 0305 hrs., August 24, 1978:

7.34 x 10-7 p Ci/ gram SECTICN 5 A reactor scram occur.ed from a power level of 80% at 0850 hours0.00984 days 0.236 hours 0.00141 weeks 3.23425e-4 months on August 24, 1978. The scram was caused by a technician incorrectly inserting a scram signal during performance of wide range power channel No. 6 surveillance testing by opening a test switch on wide range power channel No. 5.

The switching inserted a second scram signal into the 2-of-4 logic system with the channel No. 6 scram signal already present.

LACEWR Technical Specifications Section 4.2.2.22, Action g, requires an additional sampling for Iodine-131, Iodine-133 and Iodine-135, as well as srecific activity between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months af ter the completion of a thermal power change of greater than 15% of rated thermal power within one hour. The Special Peport is required to contain the information determined by this additional analysis plus Additional Information as outlined below.

Time of additional sample:

1250 hrs., August 24, 1978 l

l 1 L

t SPECIAL REPORT 78-02 SECTION 5 - (Cont'd)

Sample results: Gross Sys 1.02 p Ci/ gram Il31:

6.46 x 10-2 9 Ci/ gram j

II33:

4.90 x 10-1 u Ci/ gram I135:

5.78 x 10-1 p Ci/ gram ADDITIONAL INFOPF.ATION

l. Reactor power level starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the thermal power change 0800-1600 hrs., August 22, 1978:

62% to 67% Power Escalation 1600-2400 hrs., August 22, 1978: 67% to 77% Power Escalation 0000-0800 hrs., August 23, 1978:

77% to 78% Power Escalation 0800-1600 hrs., August 23, 1978:

78% to 80% Power Escalation 1600-2400 hrs., August 23, 1978:

79.7%

0000-0800 hrs., August 24, 1978:

79.6%

0800-0850 hrs., August 24, 1978:

80%

2.

The fuel burnup for assemblies in a symmetrical core region is depicted in Figure 5.

3.

Cleanup flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the thermal power change:

Primary Purification Flow Rates 0800-1600 hrs., August 22, 1978:

40 gpm 1600 hrs., August 22, 1978 - C800 hrs., August 23,19'i8 :

40.5 gpm 0800-1200 hrs., August 23, 1978:

40.8 gpm 1200 hrs., August 23, 1978 - 0300 hrs., August 24, 1978:

41 gpm 0300-0500 hrs., August 24, 1978:

40.5 gpm 0500-0900 hrs., August 24, 1978:

41 gpm Primary Purification Decentamination Factors (SV)

August 21, 1978:

726 August 24, 1978:

867 August 28, 1978: 1,071 4.

Offgas levels for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the thermal power change:

0800-1630 hrs., August 22, 1978:

506 Ci/d @ % 67% Power 1600-2400 hrs., August 22, 1978:

561 Ci/d @ % 77% Power 0000-08CO hrs., August 23, 1978: 585 Ci/d @ % 78% Power 0800-1600 hrs., August 23, 1978:

647 Ci/d 0 % 80% Power 1600-2400 hrs., August 23, 1978:

615 Ci/d 0000-0800 hrs., August 24, 1978: 627 Ci/d 0800-0850 hrs., August 24, 1978:

627 Ci/d ~

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SPECZAL PEPORT 78-02 SECTIOrt 5 - (Cont'd) 5.

Gross alpha activity levels for the periods 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months before and af ter the thermal power change:

0110 hrs., August 21, 1978:

6.44 x 10-7 p Ci/ gram 0305 hrs., August 24, 1978:

7.37 x 10-7 p Ci/ gram 0850 hrs., August 24, 1978: THERMAL POWER CHA! IGE 0046 hrs., August 28, 1978:

5.33 x 10-7 u Ci/ gram

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Core Average Exposure s 7.012 GWD/MTU.

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Core Average Exposure s 7.720 GWD/MTU.

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_Snecial Report 7_8_-02 a

- Quarter Cora Fuol Exposuro Estimations (GWD/MTU) as'an Indication of Regional Exposures as of August 24, 1978.

Core Average Exposure s 7.786 GWD/MTU, A

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ML20062A684

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ML20062A684

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