ML20247M213

Forwards Summary of Status of Each of Six Licensing Items Identified in V Nerses ,Including Expected Date of Completion.Required Work to Complete Items Will Be Accomplished by 890930.Position Re Reg Guide 1.68 Confirmed

ML20247M213
Person / Time
Site:	Seabrook
Issue date:	03/30/1989
From:	George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20247M217	List: ML20247M213 ML20247M279 ML20247M290
References
RTR-REGGD-01.068, RTR-REGGD-1.068, TASK-2.F.1, TASK-TM NYN-89032, NUDOCS 8904060013
Download: ML20247M213 (8)

Text

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Wew Hampshire Geage Simms Vice hesident N Jcteor hoduction Yankee NYN-89032 March 30, 1989 United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk

References:

(a) Facility Operating License NPF-56, Docket No. 50-443 (b) USNRC Letter dated March 18, 1989, " Completion of Licensing Issues and Confirmation of Commitments," V. Nerses to E. Brown

Subject:

Licensing Items Status Summary Dear Sir Reference (b) identifies six licensing items for which the NRC has requested current status and committed completion dates. Enclosure 1 to this letter contains a summary of the status of each of the six licensing items, including the expected date of completion. New Hampshire Yankee expects that, with the exception of Item 1, the required work to complete the items will be accomplished no later than September 30, 1989. New Hampshire Yankee's schedule for completing these items is consistent with the Commission's target schedule for the issuance of a final initial decision by the Atomic Safety and Licensing Board in the emergency plan proceedings.

1 In addition to the licensing items discussed in the Enclosure 1, NHY wishes to confirm.its position in regard to Regulatory Guide 1.68 (" Initial Test Programs for Water-Cooled Nuclear Power Plant"). As required by USNRC Regulatory Guide 1.68, low power testing has been sequenced and will proceed in a manner such that "the safety of the plant is never totally dependent on the l

performance of untested structures, systems and components". Any changes to l the test program described in Chapter 14 of the FSAR will be made in accordance with the provisions of 10 CFR 50.59 and will be reported in accordance with 10 CFR 50.59(b) within one month of such change.

Should you require further information regarding this matter, please contact Mr. Robert E. Sweeney at (301) 656-6100 in our Bethesda Licensing Office.

Very truly yours,

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NU Geor T m Enclosures gf p New Hompshire Yonkee Division of Public Service Compony of New Hompshire l

P.O. Box 300 = Seobrook, NH 03874 = Telephone (603) 474-9521

United States Nuclear Regulatory Commission March 30, 1989 Attention: Document Control Desk Page 2 of 2 cc: Mr. William T. Russell Regional Administrator I

, United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Mr. Victor Nerses, Project Manager Project Directorate I-3 United States Nuclear Regulatory Commission Division of Reactor Projects Washington, DC 20555 Mr. David G. Ruscitto NRC Senior Resident Inspector P.O. Box 1149 Seabrook, NH 03874 I

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i ENCLOSURE 1 TO NYN-89032 LICENSING ITEMS STATUS

SUMMARY

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LICENSING ITEMS STATUS

SUMMARY

1) Containment Systems (Section 6.2, SSER 7) .

PSNH shall add an additional pressure isolation valve in series with each of the existing check valves separating the Residual Heat Removal (RHR) and Containment Building Spray (CBS) systems, or upgrade the CBS and RHR suction piping design pressure.

Status: SSER 7 reflected NHY's commitment to complete long term actions to address this item prior to startup from the first refueling outage. The NRC accepted NHY's schedule for long term actions based on the following interim actions:

New Hampshire Yankee analyzed the effects on the CBS piping and pipe supports of varying leak rates through the four check valves isolating the CBS system from the RHR system.

CBS piping pressure boundary integrity, structural integrity and pipe support functionality were determined to be maintained under the postulated leak rates.

New Hampshire Yankee has installed a piping thermal monitoring system (PTMS) to provide plant operators with an indication of intersystem leakage. This system enables operators to initiate procedures and take corrective action to assure CBS system integrity should leakage occur.

A design change is being developed which provides long term actions to address the Containment Building Spray (CBS)/ Residual Heat Removal (RHR) system interface. This design change would add an additional check valve in series with each of the four existing check valves which provide isolation at the CBS/RHR system interface. New Hampshire Yankee will submit a complete description of this design change for NRC review and approval by April 30, 1989. Upon receipt of NRC approval, New Hampshire Yankee will expedite the implementation of this design change and will endeavor to improve upon the accepted schedule (prior to startup from the first refueling outage).

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2) Control Room Habitability (Section 6.4 SER, SSER-7. SSER 8)

PSNH shall complete the proposed modifications to the control room habitability system described in SSER 8 and shall propose conforming changes to Technical Specification 3/4.7.6.

Status: A design change has been developed to address this item. ' Details of the design change were submitted to the NRC on January 22, 1988 (NYN-88007) and June 17, 1988 (NYN-88084). This item will be complete in September 30, 1989.

Proposed Technical Specifications pertaining to this design change will be submitted by April 30, 1989.

Additionally, NHY has updated its analysis of hazardous chemicals stored at industrial facilities or transported within the vicinity of Seabrook Station. This updated hazardous chemical analysis will be submitted for NRC review by April 30, 1989.

3) Radiation Data Management System (Section 7.5.2.2, SER, SSER 5)

Qualified non-fuse dependent isolation devices shall be installed between the Class 1E portion of the Radiation Data Management. System and the non-Class 1E portion and shall be operational.

Status: SSER 5 reflects NHY's commitment to install non-fuse dependent

-isolation devices in the Radiation Data Management System prior to startup after the first refueling outage. A design change has been developed to address this item. The NRC Staff letter of March 21, 1989 indicated that the isolation device qualification documentation was acceptable. This design change will be completed by September 30, 1989.

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4) New Fuel Storage and Handling (Section 9.1 SSER 8)

The following criteria apply to storage and handling of new fuel assemblies:

a. No more than two fuel assemblies shall be out of approved shipping containers or fuel assembly storage racks at any one time,

b. PSNH shall maintain a minimum 12-inch edge-to-edge distance between fuel assemblies which are out of storage racks or shipping containers.

These criteria do not apply to those fuel assemblies in the process-of {

being transported to or from the reactor vessel.

Status: Station Operating procedures RS 0722 ("New Fuel Receipt and Inspection") and RS 0723 ("New Fuel Shipment) are enclosed (Enclosure 2 and Enclosure 3). These procedures-contain requirements which satisfy the above criteria. These requirements are contained in Section 5 (" Precautions") in RS 0722 and RS 0723.

This item is complete.

5) Fire Protection (Section 9.5.1, SER, SSER 4. SSER 5, SSER 6 SSER 7)

PSNH shall have the Heating, Ventilation and Air Conditioning System charcoal filter unit detection system and any associated modifications i dictated by the fire hazards analysis complete and operable.

Status: A design change has been developed to address this item. Details  !

of this design change were submitted to the NRC on October 9, j 1986 (SBN-1208). The design change is partially complete; the remaining work will be completed by September 30, 1989 as part of the work associated with the Control Room Habitability System (See Item 2 above).

6) Process and Effluent Radiological Monitoring and Sampling Systems, TMI Action Plan Item II.F.1 (Section 11.5 SER, SSER 2, SSER 5)

PSNH shall demonstrate that the iodine / particulate sampling system is operable and will perform its intended function. (This item may require power operation before calibration is complete.)

Status: Operability of the iodine / particulate sampling system has been demonstrated in the particulate'and radioiodine transmission modeling and analyses which were performed by SAI. The results of this effort, which indicate acceptable transmission factors for gaseous effluent sample lines, are documented in a report

-which will be submitted for NRC Staff review by May 30, 1989.

The SAI modeling and analyses indicated a need to improve the transmission factor for the Wide Range Gas Monitor (WRGM) high range sample line. As a result, a design change was developed to improve the transmission factor for this line. SAI has also-modeled the revised design and determined that the revised design yielded acceptable transmission factors. Information on the revised design has been incorporated into the SAI report referreo to above. Installation of this design change will be complete by September 30, 1989.

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ENCLOSURE 2 TO NYN-89032 RS 0722 NEW FUEL RECEIPT AND INSPECTION

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