ML20129E891

Informs That NRC Will Perform SSFI on RHR Sys.Insp Scheduled for Wks of 961118 & 1202.SSFI Info Request Encl

ML20129E891
Person / Time
Site:	Monticello
Issue date:	09/30/1996
From:	Ring M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Watzl E NORTHERN STATES POWER CO.
References
NUDOCS 9610030321
Download: ML20129E891 (4)

Text

1 e o September 30, 1996 Mr. E. Watzi Vice President, Nuclear Generation Northern States Power Company 414 Nicollet Mall Minneapolis, MN 55401

SUBJECT:

ANN 0UNCEMENT OF SAFETY S'! STEM FUNCTIONAL INSPECTION (SSFI) ON THE RESIDUAL HEAT REMOVAL (RHR) SYSTEM

Dear Mr. Watzl:

This is to inform you that the NRC will perform a safety system functional inspection (SSFI) at the Monticello Nuclear Plant. We have chosen the residual heat removal (RHR) system as the focus for this SSFI, and will perform it using NRC Inspection Procedure 93801, " Safety System functional Inspection (SSFI)". The inspection's onsite activities are scheduled for the weeks of November 18 and December 2, 1996. The details of this inspection, including the system chosen for the SSFI, were communicated to your staff (Mr. C. Schibonski, General Superintendent Engineering) on Thursday, September 26, 1996.

The inspection will assess design, operation, maintenance, surveillance, quality assurance, and corrective actions associated with the Monticello RHR system, with a concentration on the design aspects. To accomplish its objectives, the SSFI team will review a broad range of information and system activities.

In order to most effectively perform this task, we would appreciate your providing some information on the RHR system, as shown on the attached list.

We would appreciate this information being provided to the senior resident by November 1, 1996, so that she may convey it to the team. This will avoid the team making a site trip just to gather the information.

We would also appreciate it if you would arrange for a short system overview presentation immediately following the entrance on November 18. We would like to follow this presentation by a general plant tour, including as much of the RHR system as is reasonably accessible.

9610030321 960930 PDR ADOCK 05000263 G PDR k

E. Watzl 1 If you have any questions regarding the information on the attachment, or on the inspection itself, please contact Patricia Lougheed at (630) 829-9760.

Sincerely, 1

Mark Ring, Chief Lead Engineers Branch Docket No. 50-263

Enclosure:

As stated  :

cc w/ encl: Plant Manager, Monticello John W. Ferman, Ph.D.

Nuclear Engineer, MPCA State Liaison Officer, State of Minnesota  ;

Distribqilgn:

Docket File w/ encl RIII PRR w/ encl Enf. Coordinator, RIII w/ encl PUBLIC IE-01 w/ encl SRIs, Monticello, CAAI w/ encl (E-mail)

OC/LFDCB w/ encl Prairie Island w/ encl W. L. Axelson, RIII w/ encl DRP w/ enc 1 LPM, NRR w/ encl A. B. Beach, RIII w/ encl DRS w/ encl DOCUM G: l g g...ENT NAME: \DRS\M..ON092

..... ,.<ini.. 6.DRS

.. . . . n in. no. c c.,, iin . .ti..nf. i c c.,, .i t h .ti.../...i n-0FFICE RIII k RIII C RIII n AE l NAME Plougheed:nh[kRing hk MJordan N h l

'\ /I DATE 09/2-7/96 09/4 7 /96 09/ 3 o/96 l OFFICIAL RECORD COPY l

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030090 1

1 Attachment SSFI Information Reauest

1. Residual heat removal (RHR) design basis document.

2. Procurement specifications for all major equipment, such as pumps, heat exchangers, valves, and orifices.

3. Thermal and hydraulic calculations and analyses, including a summary of normal and accident heat load inputs to the RHR system.

4. Electrical calculations associated with the RHR system.

5. Certified pump curves (witnessed test curves.)

6. Cross-sectional drawings of major RHR equipment such as pumps and heat exchangers.

7. P& ids of the RHR system, and any interconnected or auxiliary systems.

8. Electrical schematics and single-line drawings showing the power i supplies to the major RHR components.

9. Isometrics for the RHR system piping. l l

10. RHR analyses supportir.g single active failure adequacy.

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11. RHR flow data for system components and heat transfer data for heat exchangers and coolers for various modes.

12. RHR water hammer or surge pressure protection information. l

13. Vendor manuals for the major components of the RHR system.

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14. RHR system operating procedures for system alignment, normal operation,  !

and abnormal condition or emergency response.

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15. RHR system response procedures, i.e. those procedures for responding to and evaluating control room or local alarms that may lead into the system operating procedures requested above, i

16. Training information for licensed and non-licensed operators including lesson plans, training text, handout material, and task performance measures.

17. Training information for maintenance personnel in regard to activities performed on the RHR system.

18. Preventive and corrective maintenance procedures for the RHR system, its components, related instrumentation, and power supplies.

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19. Maintenance history for the major components of the RHR system over the last two years.

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20. Information on RHR system and component reliability and availability for j the last two years.  ;

21. A listing of any RHR system maintenance activities scheduled during the inspection.

22. A listing of RHR system scheduled surveillances, including due date, critical date, and date the surveillance was last performed.

23. The completed preoperational test procedure.

24. Copies of RHR surveillance procedures.

25. A listing of RHR components included in the IST program and the results of their IST testing. i P

26. Results of heat exchanger testing, if performed (last three tests on each heat exchanger.)  !

27. Quality verification activities (surveillance and audits) related to the )

RHR system over the last two years. '

28. Onsite and offsite review committee meeting minutes for the past six months.

29. Deviation reports, non-conformance reports, or other deficiency logs pertaining to the RHR system (for the last two years.)

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