ML20079G038

Forwards Application for Amend to Licenses DPR-42 & DPR-60, to Provide Assurance of Reactor Coolant Vent Sys Operability & Reliability,Implementing Requirements of NUREG-0737,Item II.B.1

ML20079G038
Person / Time
Site:	Prairie Island
Issue date:	01/13/1984
From:	Musolf D NORTHERN STATES POWER CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20079G042	List: ML20079G038 ML20079G046 ML20079G054
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-TM TAC-53458, TAC-53459, NUDOCS 8401190387
Download: ML20079G038 (2)

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Noithem States Power Company 414 Nicollet Mae Minnearchs Minnesota 55401 Telephone (612) 330-5500 January 13, 1984 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 License Amendment Request dated January 13, 1984 Reactor Coolant Vent System Attached are three originals and 37 conformad copies of a request for a change of Technical Specifications. Appendix A, of Operating Licenses DPR-42 and 60. Also attached is one copy of the License Amendment class determination and a check in the amount of $4,400.00 for the amendment fee.

This submittal proposes changes to Sections 3.1 and 4.0 of the Prairie Island Technical Specifications. The proposed changes implement require-ments of NUREG-0737, Item II.B.1 and are in response to NRC Generic Letter No. 83-37, dated November 1, 1983.

Exhibit A describes the proposed change, reason for change and significant hazards evaluation. Exhibit B contains the revised Appendix A pages.

The NRC Safety Evaluation of the Prairie Island reactor coolant vent system, dated September 19, 1983, identifies four open items which require resonse from Northern States Power Company. The following are submitted in response:

1. The Prairie Island reactor ecolent vent system was fabricated and tested in conformance with Standard Review Plan Section 5.2.3. The reactor coolant vent system design change records are available for NRC verifi-cation.

2. The reactor coolant vent system was designed in accordance with the requirements of the following codes and stan1ards:

a. ASME Boiler and Pressure Vessel Code Section II (Summer, 1979) and Section III (Summer, 1976).

8401190387 840113 0 PDR ADOCK 05000282 )

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NORTHERN CTATES POWER COMPANY Dir, NRR January 13, 1984 Page 2

b. ANSI Standards B16.11, B16.25, B16.5 and B31.1.

c. Regulatory Guide 1.44.

3. The susceptibility of the Target Rock valve system to common mode failure has been evaluated, and in response the vent valve located in the containment atmosphere discharge line was inverted per the supplier's recommendation. Valve manufacturer tests indicate that this valve orientation will limit the amount of liquid discharged from a closed downstream valve following the opening of an upstream valve to less than 10.9 cc. This small quantity of liquid discharged does not present any operational concerns, nonetheless a drain line was added to the discharge of the containment atmosphere vent valve to route any discharged liquid to a floor drain.

The vent valve which discharges to the pressurizer relief tank was not inverted because any liquid discharged would be directed to the pressurizer relief tank. Tests indicate that the volume of liquid discharged following an upstream valve cycle would not be significant.

4. The reactor coolant vent system has been included in the Prairie Island inservice inspection program.

Fabrication and testing of the reactor coolant vent system has been com-pleted with the exception of the vent system pressure alarm in the control room, which J.s expected to be complete by April 1,1984. The reactor coolant vent system will be made operational upon issuance of the proposed Technical Specifications and upon completion of the related operating pro-cedures (to be completed April 1, 1984). The requirements of Section 4.18. A.1 will not be implemented until after the first cold shutdown fol-lowing issuance of the proposed Technical Specifications. The proximity of the vent system manual valves to the reactor vessel head prevents them from being blocked and tagged with the plant at power.

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David Muscif Manager - Nuclear Support S ices DMM/EFE/ dab c: Regional Administrator-III, NRC NRR Project Manager, NRC Resident Inspector, NRC MTCA Attn: J U Ferman G Charnoff Attachment 4