ML20084K044: Difference between revisions

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| number = ML20084K044
| number = ML20084K044
| issue date = 04/27/1984
| issue date = 04/27/1984
| title = Responds to NRC 840330 Ltr Re Violations Noted in IE Insp Rept 50-282/83-20.Corrective Actions:Investigation Completed & Investigation Rept Reviewed by All Operations Personnel. Special Training Sessions Held Re Tech Specs
| title = Responds to NRC Re Violations Noted in IE Insp Rept 50-282/83-20.Corrective Actions:Investigation Completed & Investigation Rept Reviewed by All Operations Personnel. Special Training Sessions Held Re Tech Specs
| author name = Larson C
| author name = Larson C
| author affiliation = NORTHERN STATES POWER CO.
| author affiliation = NORTHERN STATES POWER CO.
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| contact person =  
| contact person =  
| document report number = IES042484RLA02, IES42484RLA2, NUDOCS 8405110083
| document report number = IES042484RLA02, IES42484RLA2, NUDOCS 8405110083
| title reference date = 03-30-1984
| package number = ML20084K041
| package number = ML20084K041
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
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==Dear Mr. Keppler:==
==Dear Mr. Keppler:==


Prairie Island Nuclear Generating Plants Docket No. 50-282, License No. DPR-42 Docket No. 50-306, License No. DPR-60 In response to your letter dated March 30, 1984 which transmitted Inspection Report 50-282/83-20 (DPRP), the following information is provided.
Prairie Island Nuclear Generating Plants Docket No. 50-282, License No. DPR-42 Docket No. 50-306, License No. DPR-60 In response to your {{letter dated|date=March 30, 1984|text=letter dated March 30, 1984}} which transmitted Inspection Report 50-282/83-20 (DPRP), the following information is provided.
Violation Technical Specification 3.7.A.1 and A.5 state, in part, "A reactor shall not be made or maintained critical noe 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..."
Violation Technical Specification 3.7.A.1 and A.5 state, in part, "A reactor shall not be made or maintained critical noe 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 hours thereafter, (b) all engineered safety features are operable, and (c) both paths from the grid to the plant 4.16kv bus 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 hours thereafter, (b) all engineered safety features are operable, and (c) both paths from the grid to the plant 4.16kv bus are operable."

Latest revision as of 01:04, 26 September 2022

Responds to NRC Re Violations Noted in IE Insp Rept 50-282/83-20.Corrective Actions:Investigation Completed & Investigation Rept Reviewed by All Operations Personnel. Special Training Sessions Held Re Tech Specs
ML20084K044
Person / Time
Site: Prairie Island Xcel Energy icon.png
Issue date: 04/27/1984
From: Larson C
NORTHERN STATES POWER CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20084K041 List:
References
IES042484RLA02, IES42484RLA2, NUDOCS 8405110083
Download: ML20084K044 (3)


Text

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Northem States Power Company 414 Nicollet Maa Minneapohs. Minnesota 55401 Telephone (612) 330 5500 April 27, 1984 Mr. J. G. Keppler Regional Administrator, Region III Office of Inspection and Enforcement US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

Dear Mr. Keppler:

Prairie Island Nuclear Generating Plants Docket No. 50-282, License No. DPR-42 Docket No. 50-306, License No. DPR-60 In response to your letter dated March 30, 1984 which transmitted Inspection Report 50-282/83-20 (DPRP), the following information is provided.

Violation Technical Specification 3.7.A.1 and A.5 state, in part, "A reactor shall not be made or maintained critical noe 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 Tie Breaker No. 8 between ESF Auxiliary Supply Bus 15 and 4.16kv Unit 2, Bus 26, thus reducing the paths from 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 III violation (Supplement I).

8405110083 840508 TES042484RLA02 PDR ADOCK 05000282 [J4y G PDR 5 1984

r Mr. J.G. Keppler

-April 27, 1984 Page-2

Response

Description of'the violation is accurate. The violation was the result of a decision error (selection of inappropriate action) by a Shift Supervisor.

Corrective actions are listed below:

- An investigation was completed and the investigation report has been reviewed by all operations personnel.

- Disciplinary action with the Shift Supervisor was taken.

- A letter emphasizing the requirements for procedure changes was issued.

- Special training sessions were held which covered the technical specifications on the electrical system. These sessions were attended by operators, construction supervisors, and construction ,

engineers.

- Emphasis on technical specifications has been increased in the licensed operator requalification program and during simulator training.

Full compliance has been achieved.

Respectfully yours,

~~D

-([3L C.E. Larson Director, Nuclear Generation CEL/ts cc J. Hard G. Charnoff I

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UNITED STATLS NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 50-306 RESPONSE TO NOTICE OF VIOLATION Northern States Power Company, a Minnesota corporation, hereby submits a response to Notice of Violation dated March 30, 1984, for the Prairie Island Nuclear Generating Plant.

This letter contains no restricted or other defense information.

NORTHERN STATES POWER COMPANY By: , r N C. E. Lars6n J Director, Nuclear Generation On this g ay of df) / , 1984, before me a notary public in and for said County,~ personally appeared C. E. Larson, Director, Nuclear Generation, and being first duly sworn acknowledged that he is authorized to execute this document on behalf of Northern States Power Company, that he knows the contents thereof and that to the best of his knowledge, information and belief, the statements made in it are true and that it is not interposed for delay.

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