ML19296D607

Responds to NRC 800104 Ltr Re Violation Noted in Insp Rept 50-346/79-29.Corrective Action:Bistable Setpoints Properly Reset

ML19296D607
Person / Time
Site:	Davis Besse
Issue date:	02/01/1980
From:	Crouse R TOLEDO EDISON CO.
To:	Heishman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19296D606	List: ML19296D607
References
1-115, NUDOCS 8003070089
Download: ML19296D607 (2)

Text

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February 1,1980 N TOLEDO

[j[)l(j()(d Docket No. 50-3i6 A 1-c<. P ca .

License No. NPF-3 ,;"f; ' "

.v , . s u Serial No.1-115 Mr. R. F. Heishman, Chief Reactor Operations and Nuclear Support Branch, Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137

Dear Mr. 'aishman:

Toledo Edison acknowledges receipt of your January 4,1980 letter and enclosures, Appen-dix A and Inspection Report 79-29, referencing an apparent deviation from Davis-Besse Nuclear Power Station Unit 1 commitments to the Nuclear Regulatory Commission listed as an "Inf raction" in Appendix A.

Infraction: Technical Specification 3.4.1.a requires that in Modes 1 and 2, with one reactor coolant pump not in operation, STARTUP and POWER OPERATION may be initiated and may proceed provided THERMAL POWER is restricted to less than 78.3% of RATED THERMAL POWER and within four hours the setpoints for the following trips have been reduced to the values specified in Specification 2.2.1 for operation with three reactor coolant pumps operat-ing: (1) High Flux, (2) Flux- 6 Flux-Flow The surveillance portion of that specification requires that the Reactor Protective Instrumentation channels specified be verified to have had their trip setpoints changed to the values specified in Specification 2.2.1 for the applicable number of reactor coolant pumps operating....

e (a) Within four hours after switching to a different pump combination if the switch is made while operating.

Contrary to the above:

On November 26, 1979, while in Mode 1, Reactor Coolant Pump 1-2 was tripped, and the high flux trip setpoint was not changed to the value specified in Table 2.2.1 within four hours af ter the change to three reactor coolant pump operation. The flux- 6 flux-flow trip setpoint was not verified to have its setpoint changed to the value specified in Technical Specification 2.2.1 within four hours after change to three reactor coolant pump operation.

FEB 7 1980 THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. OH'O 43552 80 0307 0()/3d

February 1, 1980 Docket No. 50-346 License No. NPF-3 Serial No. 1-115 Page 2 Response: a) The high flux trip bistables were reset to a 78.5% setpoint, as obtained from the Shift Foreman, within four hours after reactor power was reduced and Reactor Coolant Pump 1-2 was tripped. Dur-ing the subsequent shift log review, approximately eight hours later, this value was discovered to be in excess of 78.3%, which is the maximum allowed per the Technical Specification 2.2.1 for three reactor coolant pump operation. The bistable setpoints were then properly reset within the requirements of Tec~nnical Specifica-tion 3.0.3, Limiting Condition for Operation.

The flux- A flux-flow trip setpoint was not verified up to the time that the subsequent shift turnover revealed a problem with the high flux trip setpoint. The flux- 6 flux-flow trip, however, will auto-matically adjust to a three reactor coolant pump setpoint due to the reduced reactor coolant system flow input. The adjusted setpoint was there upon verified, but was conservatively reset and verified shortly afterwards pending resolution of questions regarding the bases of Technical Specification 2.2.1.

b) The cacse for incorrectly setting the high flux trip setpoint and not verifying the flux- A flux-flow setpoint has been attributed to procedural deficiencies in that correct and concise information was not provided. The EP 1202.06, Reactor Coolant Pump and Motor Emer-gency Procedure, and PP 1102.04, Power Operations Procedure used dur-ing the trip of Reactor Coolant Pump 1-2 do not reference the operator to Technical Specification 3.4.1 or its surveillance requirements.

Modifications have been made to these procedures as corrective action taken to avoid further non-compliance. The NSSS vendor has clarified the problems surrounding the technical content of the bases for Tech-nical Specification 2.2.1 and a new surveillance test, ST 5030.18, Check of Flux- 21 Flux-Flow Bistable Setpoint was prepared to explicitly cover this situational surveillance requirement.

c) Full compliance has been achieved as of January 25, 1980.

Yours very truly, ffk= L ^

Richard P. Crouse Vice President, Nuclear RPC/TDM/SMQ/lj k