ML20039A741

Responds to Generic Ltr 81-34, Safety Concerns Associated W/Pipe Breaks in BWR Scram Sys. Info Suppls 810615 & 0722 Ltrs.Responses Statisfy NRC Requests

ML20039A741
Person / Time
Site:	Zimmer
Issue date:	12/15/1981
From:	Borgmann E CINCINNATI GAS & ELECTRIC CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0803, RTR-NUREG-803 GL-81-34, NUDOCS 8112210238
Download: ML20039A741 (4)

Text

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.THE CINCINNATI GAS & ELECTRIC COMPANY set CINCINNATLOHIO 4 5208 E. A. BORG MANN SENtOW V5CE PRE $10ENT December 15, 1981

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Docket No. 50-358

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Mr, Harold Denton, Director 2

6 ete n,hdiIg L Office of Nuclear Reactor Regulation 3

U.S. Nuclear Regulatory Commission

'N Washington, D.C.

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ZIMMER NUCLEAR POWER STATION Y tN UNIT 1 - PIPE BREAKS IN THE BWR SCRAM SYSTEM (GENERIC LETTER 81-34)

Dear Mr. Denton:

This is in response to the August 31, 1981 NRC Generic Letter 81-34, Safety Concerns Associated with Pipe Breaks in the BWR Scram-System, from Darrell G. Eisenhut to all GE BWR Licensees.

Generic Letter 81-34 forwarded NUREG-0803, " Generic Safety Evaluation Report Regarding Integrity of BWR Scram System Piping."

CG&E has made two submittals to the NRC on this topic:

A generic response on June 15, 1981 and a plant ~-

specific response on July 22, 1981.-

The plant specific response was in reply to an April 24 NRC letter which requested information specifically for the Zimmer Station.

Attached.is supplementary information relative to pipe breaks in'the BWR:

Scram System which supplements the information previously sent.

to the Staff by CG&E letters of June 15, 1981 and July 22,.1981.

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To:

Mr. Harold Denton, Director December 15, 1981 Re:

Wm. H.

Zimmer Nuclear Power Station -

Page #2 Unit 1 - Pipe Breaks in the BWR Scram System (Generic Letter 81-34)

CG&E believes that the information supplied in the June 15, 1981, July 22, 1981 and this current letter satisfies the information requested by the NRC.

Very truly yours, THE CINCINNATI GAS & ELECTRIC COMPANY

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By E. A. BORGMANN EAB: dew i

Enclosure cc:

John H. Frye III M.-Stanley Livingston Frank F. Hooper Troy B. Conner, Jr.

James P. Fenstermaker Steven G.

Smith William J. Moran J.

Robert Newlin Samuel H. Porter James D. Flynn W.

F. Christianson James H. Feldman, Jr.

John D. Woliver Mary Reder David K. Martin George E.

Pattison Andrew B. Dennison State of Ohio

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County of Hamilton)ss Sworn to and subscribed before me this /8k day of December, 1981.

Dhuosi$ fYdd Notap Public fdARGARET L HUBER -

fictary P4!:c, Shta Cf Ohio Lfy Comtr.lnica Expires Aug.14 ana j

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,-.mvwx;;nmu-Docket-No. 50-358 ATTACHMENT WM.

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ZIMMER NUCLEAR POWER STATION UNIT 1 The following information follows Table 5.1 of NUREG-0803:

1.

Periodic Inservice Inspection and Surveillance for the SDV System:

CG&E will implement an ISI program for Zimmer Station's SDV system meeting the requirements for class 2 piping-in the Section XI ASME code.

This program will be implemented consistent with the ISI program at'Zimmer Station.

2.

Threaded Joint Integrity:

This is not applicable to Zimmer Station since we have no threaded joints in the system.

3.

Seismic Design Verification:

CG&E is currently reanalyzing the CRD/SDV for seismic loading.

Final analysis is due to be complete at the

- end of February, 1982.

4.

HCU-SDV Equipment Procedures Review:

A review of all surveillance, maintenance and inspection procedures will be accomplished prior to O.L.'to ensure SDV integrity is not defeated.

Modification procedures will be evaluated as they come up and prior to use.

5.

Environmental Qualification of Prompt Depressurization Function:

Review of Environmental Qualification for all safety-related electrical equipment located in harsh environments at the Zimmer Station is near. completion.

This review is being performed in accordance with NUREG-0588 to the postulated accident' environmental parameters.

These parameters envelope the' reactor building environment predicted to result.from'a postulated rupture in the SDV system as analyzed by General Electric.

In cases where qualification'cannot be verified,'the. equipment will be retested or replaced.

Docket No. 50-358 Page #2 6.

As-built Inspection of SDV Piping and Supports:

Construction and modification is currently taking place in these areas.

A complete as-built inspection of this piping will be done after all modifications are complete.

7.

Improvement of Procedures:

CG&E will follow the recommendations of the BWR Owners Group on procedures dealing with this postulated break.

8.

Verification of Equipment Designed for Water Impingement:

Refer to CG&E's response to item 5 above.

9.

Verification of Equipment Qualified for Wetdown by 212 F Water:

Refer to CG&E's response to item 5 above.

10.

Verification of Feedwater and Condensate System Operation Independent of the Reactor Building Environment:

At Zimmer Station, operation of the feedwater and condensate system is independent of the reactor building environment.

11.

Evaluation of Availability of HPCI - LPCI (sic) Turbines Due to High Ambient Temperature Trips:

Zimmer Station does not have an HPCI system.

It has an HPCS (High Pressure Core Spray) which is an electrically driven pump that does not have a high ambient temperature trip and therefore Zimmer Station maintains this high pressure water source.

With regard to the apparent typo (should be RCIC not LPCI), the RCIC high ambient temperature trip has not been established.

This temperature will be determined during the startup program.

12. Verification of Essential Components Qualified for Service at 212*F and 100% Humidity:

Refer to CG&E's response to item 5 above.

13. Linitation of Coolant Iodine Concentrations to Standard Technical Specification Values:

Per page 5-5 of NUREG-0803 "New operating licenses will include STS" with respect to coolant activity levels.

Zimmer Station therefore will meet. this by definition since the OL has not been issued yet.