ML20206F544

Forwards List of Open Items,Including 851226 Overcooling Event Concerns,Requiring Util Action Per 860523 Telcon.Items Listed in Areas a & B Should Be Addressed in Restart Rept

ML20206F544
Person / Time
Site:	Rancho Seco
Issue date:	05/29/1986
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Julie Ward SACRAMENTO MUNICIPAL UTILITY DISTRICT
References
TAC-60462, NUDOCS 8606240516
Download: ML20206F544 (6)

Text

-_ . _ .

, May 29,1986 Docket No. 50-312 Mr. John E. Ward Assistant General Manager, Nuclear (Acting)

Sacramento Municipal Utility District 6201 S Street P. O. Box 15830 Sacramento, California 95813

Dear Mr. Ward:

Enclosed is a list of open items, according to our records, that require action by SMUD. The list was used in the telephone discussion held between the NPC staff (NPR and Region V) and your staff on May 23, 1986.

The items listed in the A and B areas are expected to be addressed in your 1 restart report. Your staff indicated that other issues such as nanagement restructuring and steam generators will also be included in your restart report.

We requested that you review your schedules for completing the licensing actions listed in C and update your integrated schedule accordingly. While not part of your restart report, we expect to include the status of licensing actions in our briefing to the Commission.

Sincerely, m: win 1L SIG?Q BT JCC 7. SM4' John F. Stolz, Director PWR Project Directorate #6 Division of PWR Licensing-B

Enclosure:

As Stated cc w/ enclosure:

See next page DISIM84 UGH ACRS-10 Gacket Filg.) BGrimes NRC FUR JPartlow L PDR SMiner PBD-6 Rdg RIngram FMiraglia Gray File OELD EBrach EJordan H0rnstein AAH PBD-6 PBD-6 BD 6 SMiner; RWeller J 5/zs/86 5/M/86 5b /

8606240516 e60529 PDR ADOCK 05000312 g PDR

Mr. R. J. Rodriguez Rancho Seco Nuclear Generating Sacramento Municipal Utility District Station cc:

Mr. David S. Kaplan, Secretary Sacramento County and General Counsel Board of Supervisors Sacramento Municipal Utility 827 7th Street, Room 424 District Sacramento, California 95814 6201 S Street P. O. Box 15830 Ms. Helen Hubbard Sacramento, California 95813 P. O. Box 63 Sunol, California 94586 Thomas Baxter, Esq.

Shaw, Pittman, Potts & Trowbridge 1800 M Street, N.W.

Washington, D.C. 20036 Mr. Ron Columbo Sacramento Municipal Utility District Rancho Seco Nuclear Generating Station 4440 Twin Cities Road Herald, California 95638-9799 i

Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident Inspector / Rancho Seco c/o U. S. N. R. C.

14410 Twin Cities Road Herald, California 95638 Regional Administrator, Region V U.S. Nuclear Regulatory Commission '

1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Director Energy Facilities Siting Division Energy Resources Conservation &

Development Commission 1516 - 9th Street Sacramento, California 95814 Mr. Joseph 0. Ward, Chief Radiological Health Branch State Department of Health Services 714 P Street, Office Building #8 Sacramento, California 95814 l

Sl1.s)6(o LIST OF OPEN ITEMS REQUIRING ACTION BY SMUD ,

l A. Areas of Concern Relating to December 26, 1985 Overcooling Event (NRR and Pegion V)

1. Loss of D.C Power to ICS/NNI root cause

- control room instrumentation failure (e.g. main feedwater flowmeter 50% readout)

FMEA i

- power supply monitors

- integrity of electrical terminations

2. Plant Response on Loss of ICS/NNI ADV and TBV

- startup and MFW control valves, MFP speed control independent of ICS for AFW control valves, ADV and TBV

- secondary steam system valve isolation walkdown check -

capability of isolation from control room

- response to return of ICS power

3. Make up/HPI Pump Failure root cause -

- interlocks on water supply sources make up pump repair

4. Overcooling Effects and Reactor Vessel and Steam Generators analysis of internal transient on vessel and steam generators.

~ - license amendment to clarify cool down rate

- technical basis for PTS guidelines

- potential for core lift

5. Radiation Monitor Damage root cause effects of containment isolation

- systems required following ESFAS

6. Flooding of Main Steam Headers

- evaluate steam header supports ..

2

7. Plant Maintenance and Testing

- evaluate maintenance program manual valve maintenance

- preventative maintenance and other deficiencies

- troubleshooting for root cause determination '

- repair damaged valves systems test program

8. Training and Operator Performance adequacy of licensed operator and non-licensed operator training o ICS off normal operation o operation on make up system o AFW throttling o AFW pump trip criteria o emergency plan o communications o ADV, TBV operation o differences between B&W simulator and Rancho Seco plant o operation of manual valves (including hand jacks) o plant modifications, procedural changes and additions minimum staffing requirements security / safety interfaces

~

9. Normal and Emergency Procedures event related procedure (loss of ICS power)

- adequacy of AT0G for PTS adequacy of health physics and emergency procedures

- adequacy on Annunciator Procedures Manual methodology for ensuring changes properly reflected in procedures

10. Human Engineering Deficiencies

- braker position indication valve position indication on TBV, ADV and AFW flow control valves "ICS and " Fan Failure" alann

11. Retrospective Issues

- adequacy of FSAR analysis EFIC system o installation delay ..

o current schedule o NUREG-0737 II El.2 justification

.o ,

- modifications and improvements of other facilities

- reliability of ICS o bulletin 79-27 o CR-3 Feb/80 loss of NNI power o NUREG-0667 i o partial loss of NNI at Rancho Seco March /84

- probability of PTS events o BAW-1791 B. Region V Additional Items

1. Post Accident Sampling System

- system modifications

- procedures and training testing

2. Control Room /TSC Emergency HVAC System adequacy of design and installation modifications loading A train on diesel generator

3. 125V D.C. Station Batteries adequacy of batteries replacement

4. Radioactive Liquid Effluent Releases offsite contamination

- Technical Specification deficiencies long tenn resolution

5. Emergency Plan meteorology program improvements training procedures and dose assessment C. Licensing Areas (NRR)

1. Regulatory Guide 1.97

- implementation ,,

2. Control Room Design Review (DCRDR)

- implementation l

1 J

3. SPDS upgrade to safety grade  ;

isolation devices modifications (fomat) ,

4 Spent Fuel Pool Cooling System upgrade of cooling return line

5. Inadequate Core Cooling Instrumentation

- implementation

6. Class IE Electrical System

- TDI diesel generator qualification

- complete class IE electrical system in NSEB

7. Low Temperature Overpressure Protection

- install bypass valve in make up

8. Security Modifications

~

NSEB, diesel generator building

9. Relief and Safety Valve Test

- install pressurizer safety valve supports

10. Reactor Coolant Pump Seal Damage

- automatic initiation of seal injection on loss of offsite power

11. Appendix R .

- complete alternate shutdown (additional isolation switches)

- automatic fire suppression NSEB (areas 81 & 82)

- circuit separation of NSEB HVAC cable reroute ~HPI train A

12. Seismic Assessment of Foothills Fault System

13. Compliance with 10 CFR 50.46 (NUREG-0737 II.K.3.31) ,

l

14. Diesel-Generator reliability Technical Specifications (GL 84-15) 1

15. Revised Technical Specifications for containment isolation valves

16. 10 CFR 50.62 Requirements for Reduction of Risk from ATWS Events

- - - _ _ . . . . -- - .. , . - . -