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Notice of Violation from Insp on 831118-1207.Violation Noted:On 831117,while Reactor Critical & Above 200 F, Licensee Racked Out Bus Tie Breaker 8 Between ESF Auxiliary Supply Bus 15 & 26 Reducing Paths from Grid to 4.16 Kv
	ML20244C879
Person / Time
Site:	Prairie Island
Issue date:	03/30/1984
From:	James Keppler; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	;
Shared Package
ML20087P190	List: ML20244C879;
References
	EA-83-143, NUDOCS 8404060143
	Download: ML20244C879 (14)
	v • d • e

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SCIICE OF V10LAT10:,

':crthern States Power Company Doc;#: Mu. 50-282 rairie Island Nuclear Generating Plant Licenn *:o. DPR-42

" nit 1 EA F 3- 1/ 3 A special inspection was conducted by Messers. J. E. Hard and P. L. Hartmann of this of fice durin$ the period November 18 through Decen.ber 7, 1983. This special inspection concerned the circumstances surrounding reduced offsite

. power supplies to an Emergency Saf ety Feat ures auxiliary supply bus.

.On November 17, 1983, the licensee discovered that during the time that the

- Unit 1 diesel generator was out of service, Bus Tie Breaker No. 8 between ESF Auxiliary Supply Bus 15 and 4.16kv Unit 2 Bus 26 was racked out. This reduced the number of paths from the transmission grid to safety Bus 15 to only one.

Since this condition existed for about 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months while *the plant was in operation, the licensee violated a Technical Specification Limiting Condition for Operation (LCO).

As a result of this inspection and in accordance with the NRC Enforcement Policy, 10 CFR Part 2, Appendix C the following violation was identified.

Technical Specification 3.7.A.1 and A.5 state, in part, "A reactor shall not be made or maintained critical nor shall it be heated or maintained above 200*F unless all of the following requirements are satisfied for the applicable unit...at least two separate paths from the transmission grid to the plant 4.16kv safety buses...both diesel generators are operable..."

Technical Specification 3.7.B.2 states, in part, "A reactor shall be placed in the cold shutdown condition if the requirements of Specification TS.3.7.A cease to be satisfied. During startup operation or power operation, any of the following conditions of inoperability may exist for the times specified provided startup operation is discontinued until operability is restored....

One diesel generator may be out of service for a period not to exceed seven days (total for both diesel generators during any consecutive 30 day period) provided (a) the operability of the other diesel generator and its associated diesel driven cooling water pump are demonstrated immediately and at least once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, (b) all engineered safety features are operable, and (c) both paths from the grid to the plant 4.16kv bus are operable."

Contrary to the above, on November 17, 1983, while the reactor was critical and above 200*F, the licensee racked out Bus Tic Breaker No. 8 between ESF Auxiliary Supply Bus 15 and 4.16kv Unit 2, Bus 26, thus reducing the paths from i the grid to the plant 4.16kv bus to one while the diesel generator associated with Bus 15 was unavailable.

This is a Severity Level}Lxiolat4cnJ, Supplement I).

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CP PKG PRAIRIE -ISLAND REV 0 /

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JOYCE } i Author's Name:

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Document Comments:

Rec'd from RIII 2/15/84

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a MEMORANDUM FOR: Jane A. Axelrad, Director, Enforcement Staff, IE FROM: William H. Schultz, Enforcement Coordinator, Region III

SUBJECT:

- NORTHERN STATES POWER - PRAIRIE ISLAND PROPOSED CIVIL PENALTY The enclosed documents proposing c.ivil penalty action under the NRC Enforcement Policy are forwarded for your review and concurrence. The proposed action is in accordance with the Janu,,ary 30, 1984 memo from G. R. Klingler.

W. H. Schultz Enforcement Coordinator Attachments:

1. Draft ltr to licensee w/ Notice of Violation and Proposed Imposition of Civil Penalty

2. Inspection Report No. 50-282/83-20(DPRP)

3. Referenced Technical Specifications cc w/attachs:

J. Lieberman, ELD Regional Enforcement Coordinators RI, RII, RIV, RV RIII RIII RIII RIII RIII RIII RIII Jackiw/sv Shafer Norelius Lewis Schultz Davis Keppler 02/09/84 l

L _ ___- __ _.

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i Docket No. 50-282

. I Northern States Power Company ~

ATTN: Mr. C. E. Larson Director of Nuclear

l Generation 414 Nicollet Mall Minneapolis, MN 55401 i Gentlemen:

This _ refers to the special safety inspection conducted by Messrs.

J. E. Hard and P. L. Hartmann of this office during the period November 18 through December 7, 1983, of activities at the Prairie Island Nuclear Generating Plant authorized by NRC Operating License No. DPR-42. This special inspection concerned the circumstances surrounding reduced offsite power supplies to an Engineered Safety Features auxiliary supply bus-that occurred and was corrected by you on November 17, 1983. The results of this inspection were discussed on December 7, 1983, during an enforcement conference held in your corporate offices between Messrs. D. W. McCarthy, D,-

E. Gilberts, yourself, and other NSP personnel, and Mr. A. B. Davis and other members of the NRC staff.

The inspection revealed that on November 17, 1983 you discovered that during the time the Unit 1 Diesel Generator was out of service, Bus Tie Breaker No. 8 between ESF Auxiliary Supply Bus 15 and 4.16kv Unit 2 Bus 26 was racked out. This reduced the number of_ paths from the transmission grid to safety Bus 15 to_only one. Since this condition existed for about 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months while the plant was in operation, you violated a Technical Specification Limiting Condition for Operation (LCO).

This violation has been categorized as a Severity Level III violation as described in the General Policy and Procedure for NRC Enforcement Actions (Appendix C to 10 CFR 2). This Severity Level III violation involved a Technical Specification Limiting Condition for Operation (LCO) being exceeded where the appropriate Action Statement was not satisfied that resulted in'a degraded cond,ition; and sufficient information existed which should have alerted the licensee that he was in an Action Statement Condition. Sufficient information in this case was the availability of system procedures which provide the proper configuration for the electrical system and the opportunity for more than one operator to recognize the violation. In addition, administrative controls that are designed to provide added reviews when critical work is performed, were not adequately implemented. The base value of Civil Penalty for a Severity Level III violation is $40,000. However, after considering: (1) your prompt and CERTIFIED MAIL RETURN RECEIPT REQUESTED ,.

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extensive corrective action that in the short term included expeditious restoration of the degraded equipment, investigation, and disciplinary action and in-the~1ong term included special training, review of the requalification program, and dissemination of the investigation report and (2) your prompt actions to develop your Positive Discipline Program in response to the increase,in event reports attributed to personnel L

errors, the base penalty for this event has been reduced by 50%. After consultation with the Director of the Office of Inspection and Enforcement,

'I have been authorized to issue the enclosed Notice of Violation and Porposed linposition of Civil Penalty in the amount of Twenty Thousano Dollars. ,

You are required to respond to the enclosed Notice of Violation and Proposed Imposition of Civil Penalty and should follow the instruction in.the Notice when preparing your response. In addition to your. response to the specific violation your response to the enclosed Notice should address corrective t actions you have taken or planned to improve the management effectiveness for l- -ensuring that Technical Specification requirements are met and for ensuring personnel performing safety-related activities are properly trained. Your written reply to this letter and the results of future inspections will be considered in determining whether further enforcement actions is appropriate.

In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2 Title 10, Code of Federal Regulations, a copy of this letter and the enclosures will be placed in the NRC's Public Document Room.-

The response directed by this letter and the enclosed Notice are not subject to the clearance procedure of the Office of Mana'gement and Budget as required by the Paperwork Reduction Action of 1980, PL 96-511.

Sincerely, James G. Keppler Regional Administrator

Enclosure:

Notice of Violation and Proposed Imposition of Civil Penalty cc w/ encl:

E. L. Watzl, Plant Manager DMB/ Document Control Desk (RIDS)

Resident Inspector, RIII Prairie Island Resident Inspector, RIII Monticello John W. Ferman, Ph.D.,

Nuclear Engineer, MPCA

- ._.__ _________-_-_ - _ ~

NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF CIVIL PENALTY Northern States Power Company Docket No. 50-282 Prairie Island Nuclear Generating Plant License No. DPR-42 EA 83-On November 17, 1983, the licensee discovered that during the time that the Unit 1 diesel generator was out of servicd, Bus Tie Breaker-No. 8 between ESF Auxiliary Supply Bus 15 and.4.16 KV Unit 2 Bus 26 was racked out. This reduced the number of paths from the transmission grid to safety Bus 15 to only one. Since this condition existed for abo; 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months while the plant was in operation the licensee violated a Technical Specification Limiting Condition for Operation,(LCO).

To emphasize the importance of being aware of operating requirements and operating the facility in accordance with the Technical Specification and the plant Administrative Control procedures, the NRC proposes to impose a Civil Penalty in the amount of Twenty Thousand Dollars. The base civil penalty for a Severity Level III violation is $40,000. However, because of prompt and extensive corrective action to prevent recurrence, the civil penalty has been decreased by $20,000. In accordance with the General Policy and Procedure for NRC Enforcement Actions (10 CFR Part 2, Appendix C) 47 FR 9987 (March 9, 1982), and pursuant to Section 234 of the Atomic Energy Act of 1954, as amended ("Act"), 42 U.S.C. 2282, PL 96-295, and 10 CFR 2.205, the particular violation and the associated civil penalty is set forth below:

Technical Specification 3.7.A.1 and 5 states, in part "A reactor shall not be made or maintained critical nor shall it be heated or maintained above 200 F unless all of the following requirements are satisfied for the applicable unit...at least two seperate paths from the transmission grid to the plant 4kv safety buses. .both diesel generators are operable. "

Technical Specification 3.7.8.2 states, in part, "A reactor shall be placed in the cold shutdown condition if the requirements of Specification TS.3.7. A cease to be satisfied. During startup operation or power operation, any of the following conditions of inoperability may exist for the times specified provided startup operation is discontinued until operability is restored..

One diesel generator may be out of service for a period not to exceed seven days (total for both diesel generators during any consecutive 30 day period) provided (a) the operability of the other diesel generator and its associated j diesel driven cooling water pump are demonstrated immediately and at least j once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereaf ter, (b) all engineered safety features are operable, and (c) both paths from the grid to the plant 4kV bus are operable." '

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5 Notice of Violation 2 Contrary to the above, on November 17, 1983, while the reactor was critical and above 200'F, the licensee racked out Bus Tie Breaker No. 8 between ESF Auxiliary Supply Bus 15 and 4.16 KV Unit 2, Bus 26, thus reducing the paths from the grid to the plant 4KV bus to one. ,

This is a Severity Level III violation (Supplement I).

(Civil Penalty - $20,000).

Pursuant to the provisions of 10 CFR 2.201, Northern States Power Company

~

is.hereby required to submit to the Director, Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commissian, Washington, D.C. 20555, and a copy to the Regional Administrator, U.S. Nuclear Regulatory Commission, Region III, 799 .loosevelt Road, Glen Ellyn, IL 60137, within 30 days of the date of this Notice a written statement or explanation', including for each

. alleged violation: (1) admission or denial of the alleged violation; (2) the <

reasons for the violation, if admitted; (3) the corrective steps which have been taken and the results achieved; (4) the corrective steps which will be taken to avoid further violations;-and (5) the date when full compliance will i

be achieved. Consideration may be given to extending the response time for '

good cause shown. Under the authority of Section 182 of the Act, 42 U.S.C. 2232, this response shall be submitted under oath or affirmation.

i Within the same time as provided for the response required above under l 10 CFR 2.201, Northern States Power Company may pay the civil penalty in the amount of $20,000 or may protest imposition of the civil penalty, in whole or in part, by a written answer. Should Northern States Power Company fail

-to answer within the time specified, the Director, Office of Inspection and Enforcement, will issue an order imposing the civil penalty proposed above.

Should Northern States Power Company elect to file an answer in accordance with 10 CFR 2.205 protesting the civil penalty, such answer may: (1) deny the violation listed in this Notice, in whole or in part; (2) demonstrate extenuating circumstances; (3) show error in this Notice; or (4) show other reasons why the. penalty should not be imposed. In addition to protesting the civil penalty, in whole or in part, such answer may request remission or mitigation of the penalty. In requesting mitigation of the proposed penalty, the five factors contained in Section IV(B) of 10 CFR Part 2, Appendix C, should be addressed. Any written answer in accordance with 10 CFR 2.205 should be set forth separately from the statement or explanation in reply pursuant to 10 CFR 2.201, but may incorporate statements or explanations by specific reference (e.g., citing page and paragraph numbers) to avoid repetition. Northern States Power Company's attention is directed to the other provisions of 10 CFR 2.205, regarding the procedures for imposing a civil penalty.

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i Notice of Violation 4 3

Upon failure to pay any civil penalty due, which has been subsequently determined in accordance with the applicable provisions of 10 CFR 2.205, this matter may be referred to the Attorney General, and the penalty unless compromised, remitted, or mitigated, may be collected by civil action pursuant to Section 234c of the Act, 42 U.S.C. 2282. '

i FOR THE NUCLEAR REGULATORY COMMISSION !

l, James 5. Keppler Regional Administrator Dated at Glen Ellyn, Illinois this day of March 1984 I

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4 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As, a minimum, the following A.C. electrical power sources shall be OPERABLE:

a. Two physically independent circuits between the offsite transmission network and the onsite Class lE distribution system, and

b. Two separate and independent diesel generators, each with:

1. Separate day and engine-mounted fuel tanks containing a minimum volume of gallons of fuel,

2. A separate fuel storage system containing a minimum volume of I gallons of fuel, and

3. A separate fuel transfer pump.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With either an offsite circuit or diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirements 4.8.1.1.1.a and 4.8.1.1.2.a.4 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at least two offsite circuits and two diesel generators to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLO SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ,

b. With one offsite circuit and one diesel generator of the above ;

required A.C. electrical power sources inoperable, demonstrate the '

OPERABILITY of the remaining A.C. sources by performing Surveillance 9 Requirements 4.8.1.1.1.a and 4.8.1.1.2.a.4 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at S least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at least one of the y inoperable sources to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at "

1 least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTOOWN d within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Restore at least two offsite circuits g and two diesel generators to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from the time of initial loss or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c.

With verifyone diesel generator inoperable)in addition to a or b above, that:

(1) all required systems, subsystems, trains, components and devices 4

that depend on the remaining OPERABLE diesel generator as a

. source ',of emergency power are also OPERABLE, and

1 ELECTRICAL POWER SYSTEMS ACTION: (Continued)

(2) When in MODE 1, 2, or 3, the steam-driven auxiliary feed pump is OPERABLE. -

If these conditions are not satisfied within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the fol. lowing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d. With two of the above required offsite A.C. circuits inoperable, l demonstrate the OPERABILITY of two diesel generators by performing Surveillance Requirement 4.8.1.1.2.a.4 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter, unless the diesel generators are already operating; restore at least one of the inoperable offsite sources to l

OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least H0T STANDBY within l the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . With only one offsite source restored, restore at least two offsite circuits to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from time of initial loss or be in at least H0T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l

e. With two of the above required diesel generators inoperable, I demonstrate the OPERABILITY of two offsite A.C. circuits by perform-ing Surveillance Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN i within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Restore at least two diesel gener-l ators to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from time of initial loss I or be in least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD l SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l SURVEILLANCE REQUIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class 1E distribution system shall be:

a. Determined OPERABLE at least once per 7 days by verifying correct breaker alignments, indicated power availability, and

b. Demonstrated OPERABLE at least once per 18 months during shutdown by transferring (manually and automatically) unit power supply from the normal circuit to the alternate circuit.

4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

a. In accordance with the frequency specified in Table 4.8-1 on a STAGGERED TEST BASIS by:

1. Verifying the fuel level in the day and engine-mounted fuel t'a n k , .

W-STS 3/4 8-2 JUL 2 71981

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Docket No. 50-282 fl '

EA 83-143 Northern States Power Company ATTN: Mr. C. E. Larson Director of Nuclear Generation 414 Nicollet Mall Minneapolis, MN 55401 _.

-Gentlemen: -

This refers to the special saf ety inspection conducted by Messrs J. E. Hard and P. L. Hartmann of this office during the period November 18 through December 7, 1983, of activities at the Prairie Island Nuclear Generating Plant authorized by NRC Operating License No. DPR-42. This special inspection con-cerned the circumstances surrounding reduced offsite power supplies to an Engineered Safety Features auxiliary supply bus that occurred and was corrected by you on November 17, 1983. The results of this inspection were discussed on December 7, 1983, during an enforcement conference held in your corporate offices between Messrs. D. W. McCarthy, D. E. Gilberts, yourself, and other NSP personnel, and Mr. A. B. Davis and other members of the NRC staff.

The inspection revealed that on November 17, 1983 you discovered that during the time the Unit 1 Diesel Generator was out of service, Bus Tie Breaker No. 8 between ESF Auxiliary Supply Bus 15 and 4.16kv Unit 2 Bus 26 was racked out.

This reduced the number of paths from the transmission grid to safety Bus 15 to only one. Since this condition existed for about 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months while the plant was in operation, you violated a Technical Specification Limiting Condition for Operation (LCO).

This violation has been categorized as a Severity Level III violation as des-cribed in the General Policy and Procedure for NRC Enforcement Actions 10 CFR Part 2, Appendix C. This Severity Level 111 violation involved a Technical Specification Limiting Condition for Operation (LCO) being exceeded where the appropriate Action Statement was not satisfied that resulted in a degraded condition; and sufficient information existed which should have alerted the licensee that it was in an Action Statement Condition. Sufficient information in this case was the availability of system procedures which provide the proper configuration for the electrical rystem and the opportunity for more than one operator to recognize the violati,n. In addition, administrative controls that are designed to provide added rev w.s when critical work is pr.rf orced were not adequately implemented. The han value of Civil Penalty for a Severity Level III violation is $40,0no. eever, a review of your performance history

"'!IrirD MAIL l ,

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in this genert1 arca of concern did not r e et :0 tir i] c r problems , and your overall perfort:.ance as evidenced by the Syrte:.atic 'ascssn.cnts of Licensee Tc riormcnce har bcen good. For there rc Jony (la 1 4. ' < civil pencity can be

.: 2 tatt d 10T . i.fter consultctier with tia i > ; i <. r : < <f the Office of Incpec-tj..n cr.d Enfelt t<<nt, I havc d e t c n i rn , t h z. : n c. c: '

< 11t y ir varranted hel e

.2 1 bcvc l.t cn z.uthorizcd t o i st uc. tin en t i t. r t . ' ' .t . i o Violation.

You are required to respond to the encleccd Noticc of Vic1ction and should follow the in.struction in the Notice when preparing your response. In addition to your responce to the specific violation, your rerponse to the enclosed

':otice should address corrective actions : ou have taken or planned to improve your management effectiveness in ensuring tiqt t Technical S pec if ica t ion

_ requirements are met a n_d. t h a t personnel performing safety-related activities ore properly trained. Your written reply to this letter cnd the results of future inspections will be considered in determining whether further enforcement actions are appropriate.

In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the enclosures vill be placed in the NRC's Public Document R6om.

The response directed by this letter and the enclosed Notice are not subject to the cicarance procedure of the Office of Management and Budget as required by -

the Paperwork Reduction Action of 1980, PL 96-511.

Sincerely, Orlpinal signed ty JE2G G. Keppler James G. Reppler Regional Administrator

Enclosure:

Notice of Violation and Proposed Imposition of Civil Penalty ec w/ enc 1:

E. L. Watzl, Plant Manager IE:ES ELD ' RIII DMB/ Document Control Desk (RIDS) Pfer ' n - dic JLieberman WSchultz 84 I- 3//b/ 4 Resident Inspector, R111 Prairie 1sland 3

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. ! j Ren3. dent Inspector, RIII Monticello G Johi W. Ferman, Ph.D., - -

Nuclear Engineer, MPCA r[

Enforcement Coordinators ,g g E:

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ML20244C879

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