ML20214M323

Forwards Draft Outline for Plant Restart Ser,Including Preliminary Assignment of Responsibility for Writing of Specific SER Sections,For Review.Comments Requested by 860911

ML20214M323
Person / Time
Site:	Rancho Seco
Issue date:	09/08/1986
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
NUDOCS 8609110062
Download: ML20214M323 (5)

Text

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,. On 6 - o /4 g S:ptemb:r 8,1986 G - 3 ' 2-MEMORANDUM FOR: Dennis Crutchfield, Assistant Director for PWR-B.

Division of PWR Licensing-S FROM: John Stolz, Director PWR Project Directorate #6 Division of PWR Licensing-B ,

SUBJECT:

OUTLINE FOR THE RANCHO SEC0 NUCLEAR GENERATING STATION RESTART SAFETY EVALUATION REPCRT Enclosed is the draft outline for the Rancho Seco restart safety evaluation report (SER) including a preliminary assignment of responsibility (by branch) for the writing of the specific sections which make up the SER. Please review the draft SER outline and the indicated branch assignments for each SER section and identify reviewers responsible for each SER section input. Please provide me with any comments you may have by COB September 11, 1986.

We have provided preliminary copies of the outline to Region V and to IE for their comments and will coordinate them in finalizing the SER outline. We are also coordinating with DHFT in the areas of maintenance, training, and human engineering reviews.

YS h John F. Stolz, Director M PWR Project Directorate #6 Division of PkR Licensing-B

Enclosure:

As stated cc w/ enclosure: G. Edison R. Weller S. Miner G. Kalman DISTRIBUTION QcketFile]

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MEMORANDUM FOR: Dennis Crutchfield, Assistant Director '

for PWR-B ,

Division of PWR Licensing-B; D FROM: John Stolz, Director PWR Project Directorate #6 Division of PWR Licensing-B

SUBJECT:

OUTLINE FOR THE RANCHO SECO NUCLEAR GENERATING STATION RESTART SAFETY EVALUATION REPORT Enclosed is the draft outline for the Rancho Seco restart safety evaluation report (SER) including a preliminary assignment of responsibility (by branch) for the writing of the specific sections which make up the SER. Please review the draft SER outline and the indicated branch assignments for each SER section and identify reviewers responsible for each SER section input. Please provide me with any comments you may have by COB September 11, 1986.

John F. Stolz, Director PWR Project Directorate #6 Division of PWR Licensing-B

Enclosure:

As stated cc w/ enclosure: G. Edison R. Weller S. Miner G. Kalman DISTRIBUTION Docket File NRC PDR Local PDR PBD#6 Rdg FMiraglia FSchroeder Ringram Raw PBD-6 1 PBD-6 PBD#6 DIR:PWR-B SMinje.g[fi\ PBD/ man GK RWeller JStolz FMiraglia 9/ 3 /86 9/ 6 9/Y/86 9/ /86 9/ /86

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OUTLINE RANCHO SEC0 NUCLEAR GENERATING STATION SAFETY EVALUATION Pesponsibility P80#6 1. Introduction PBD#6 2. Background Discussion .+

PBD#6 2.1 Brief discussion of December 26, 1985 overcooling event PBDf6 2.2 Summary of NRC actions and correspondence PBD#6 2.3 Sunnary of Sacramento Municipal Utility District's response PBD#6 2.3.1 Plant performance and management improvement program

3. Resolution of Identified CorEerns Related to the December 26, 1985 Overcooling Event 3.1 Plant mechanNal, electriEh1 and control systems deficiencies PEICS 3.1.1 Loss nf DC power to ICS PEICS 3.1.2 Plarit' response on loss of ICS PEICS 3.1.3 Auxiliary feedwater control - EFIC installation RSB 3.1.4 Water supply to makeup /HPI pumps EB 3.1.5 Effects of overcooling event on reactor vessel and steam generators PEICS 3.1.6 Operation of radiation monitoring systems following containment isolation EB 3.1.7 Flooding of the main steam headers. Steam generator overfill PEICS 3.1.8 Main steam line failure logic system F08 3.2 System review and test program 3.2.1 Program overview 3.2.2 Program evaluation DHFT/MTB 3.3 Plant maintenance, testing and surveillance 9

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l 3.3.1 Valve preventive maintenance and manual valve operabili ty 3.3.2 AFW flow control valve operability 3.3.3 Previous maintenance deficiencies - iden-tification/ resolution 3.3.4 Troubleshooting / root cause determination DHFT/HFB 3.4. Training and operator p,erfonnance 3.4.1 Operator training 3.4.2 Minimum staffing requirements 3.4.3 Incapacitated operator 3.4.3 Potential security / safety interface issues F0B 3.5 Plant normal and emergen,cy procedures 3.5.1 Need for event-related procedures AT0Gl dequacy 7*

3.5.2 .

3.5.3 He'alth physics and emergency preparedness proce,dures 3.5.4 Annunciation procedures manual 3.5.5 Methodology for procedure updating DHFT/HFB 3.6 Human engineering considerations e

3.6.1 Simplified schematics for S1 8 S2 3.6.2 Valve position indication 3.6.3 Control room HVAC noise 3.6.4 Alarms for ICS F0B 3.7 Management considerations 3.8 Retrospective considerations RSB 3.8.1 Evaluation of FSAR accident analyses that presumed availability of non-safety systems PEICS 3.8.2 Reevaluation of responses to previous reports on B&W transients and operating experience

• (NUREG-0560,NUREG-0667,BAW-1564,Bulletin 79-27)

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4 EB 3.8.3 Probability of pressurized thermal shock incidents per BAW 1791

4. Resolution of Concerns Unrelated to the December 26, 1985 Overcooling Event PEICS 4.1 Post accident sampling system PEICS 4.2 Control room / technical support center HVAC system PEICS 4.3 125V DC station batteries e PEICS 4.4 Radioactive liquid effluent releases PEICS 4.5 Emergency plan

- Meteorology P8Df6 5. Summary and Conclusions Appendices

- ED0 action letter regarding IIT' report

- References .. . ..

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