ML13309A088
| ML13309A088 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/02/1990 |
| From: | Murley T Office of Nuclear Reactor Regulation |
| To: | SOUTHERN CALIFORNIA EDISON CO. |
| Shared Package | |
| ML13309A086 | List: |
| References | |
| NUDOCS 9001170248 | |
| Download: ML13309A088 (8) | |
Text
7590-01 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
)
Docket No. 50-206 SOUTHERN CALIFORNIA EDISON COMPANY
)
License No. DPR-13 SAN DIEGO GAS AND ELECTRIC COMPANY
)
San Onofre Nuclear Generating Station, )
Unit No. 1
)
ORDER CONFIRMING LICENSEE COMMITMENTS ON FULL-TERM OPERATING LICENSE OPEN ITEMS I.
Southern California Edison Company and San Diego Gas and Electric Company (the licensees) are the holders of Provisional Operating License No. DPR-13, which authorizes the licensees to operate San Onofre Nuclear Generating Station, Unit 1, at power levels up to 1347 megawatts thermal (rated power).
The facility is a pressurized water reactor located on the licensees' site in San Diego County, California. The license is subject to all applicable provisions of the rules, regulations, and orders of the U.S. Nuclear Regulatory Commission (NRC).
II.
On May 1, 1989, the NRC staff met with the licensees to discuss the NRC requirements for conversion of Provisional Operating License No. DPR-13 to a full-term operating license and additional actions needed to resolve NRC concerns with respect to broken bolts on the reactor vessel thermal shield.
The NRC staff explained that, for a variety of reasons, certain safety-signifi cant improvements due to be made to the facility had been unacceptably delayed over the years and that a firm, integrated schedule must be developed to 9001170248 900102 PDR ADOCK 05000206 P
PFDC
-2 complete these actions in the next two refueling outages. These actions consist of Three Mile Island Action Plan items, NRC generic letter items, and action items resulting from the integrated plant safety assessment for San Onofre Unit 1 (NUREG-0829). Collectively, these actions are referred to as the full-term operating license (FTOL) open items and are identified in Attachments 1 and 2. They are so called because their implementation is considered a prerequisite to conversion of Provisional Operating License No. DPR-13 to an FTOL.
The licensees were requested to finalize and document the schedules discussed at the meeting in a letter to the NRC, and to include their rationale for the schedules.
With respect to the thermal shield, the licensees proposed a mid-cycle inspection by not later than June 30, 1990, and a vibration monitoring and action plan to resolve the staff's concerns. These commitments were sub sequently confirmed in Amendment No. 127 issued on May 15, 1989.
The schedular request pertaining to the FTOL open items was subsequently confirmed in an NRC letter to licensees dated August 17, 1989, which reiterated the NRC staff's desire to have the FTOL open items completed in the next two refueling outages, even if the outages had to be extended in order to finish them. The letter stated that the NRC staff understood that its request did involve significant commitments that would require some time for evaluation, but requested the licensees to give the matter priority and to respond by the end of September 1989.
III.
On October 2, 1989, the licensees responded with an integrated schedule (shown in Attachments 1 and 2) for accomplishing the FTOL open items in the next
-3 two refueling outages. The plan calls for completing or resolving 18 open items in the next refueling outage (fuel cycle 11) and 21 open items in the second refueling outage (fuel cycle 12) - a total of 39 items. The schedule shows significant improvements in both scheduling and activity. The reactor vessel thermal shield would be repaired in the outage beginning June 30, 1990, rather than inspected and repair deferred until September 1991.
Also, the licensees, having determined that significant safety improvement will be achieved by upgrading the recirculation portion of the safety injection system as well as the injection portion, have included these improvements in the schedule for the cycle 12 outage. The licensees also have committed to install a plant-specific reference simulator for operator training. Taken as a whole, the licensees have made significant commitments that involve substantial safety improvements to the facility and that are responsive to the NRC staff's request.
To support this schedule as proposed, the licensees propose to combine the fuel cycle 11 refueling with repair of the thermal shield and inspection of the steam generator tubes in one extended outage (June 30, 1990, to about December 2, 1990) (Attachment 3).
The licensees are currently required to install a reactor vessel level indicating system and upgrade the core exit thermocouples by not later than startup for fuel cycle 11 in response to TMI Action Plan Item II.F.2, "Inadequ ate Core Cooling Instrumentation" (NRC order dated May 10, 1989). Because the fuel cycle 11 refueling would start much earlier than previously scheduled (June 30, 1990, rather than September 17, 1991), the licensees do not have sufficient time to design and test a reactor vessel level monitor because
-4 existing designs must be modified for installation at San Onofre Unit 1 (licensees' amendment request dated November 1, 1989).
The licensees propose to install the reactor vessel level monitor and upgrade the core exit thermo couples at the same time by not later than fuel cycle 12, and submit specific implementation plans by December 1, 1990. This would entail a relatively minor change in schedule that would involve an additional 9 months of plant operation before implementation and is acceptable.
The second schedular change involves the inspection schedule for the steam generator tubes which would be required to be inspected by March 7, 1990 (licensees' amendment request dated October 31, 1989). The licensees request that this inspection be coordinated with the long outage beginning June 30, 1990. This revised schedule for inspection is acceptable, since the licensees have shown that steam generator tube corrosion has stabilized, and this is a relatively modest 4-month extension of a 24-month inspection interval.
IV.
I find that the licensees' commitments collectively represent significant safety improvements to the facility and are acceptable. In view of the fore going, I have determined that the public health and safety require that the licensees' commitments contained in their letter of October 2, 1989, be confirmed by order.
Accordingly, pursuant to Sections 103, 161b and 161i of the Atomic Energy Act of 1954, as amended, and the Commission's regulations in 10 CFR 2.204 and 10 CFR Part 50, IT IS HEREBY ORDERED that Provisional Operating License No.
DPR-13 be modified as follows:
Licensees shall implement the schedular commitments contained in their letter of October 2, 1989, as summarized in Attachments 1, 2, and 3
-5 hereto with respect to the specific activities to be conducted at outages for fuel cycles 11 and 12 (exact dates of the outages may be revised from time to time).
Specific plans for implementation of Item II.F.2, "Inadequate Core Cooling Instrumentation System" (Generic Letter 82-28), shall be submitted to the NRC for approval by no later than December 1, 1990.
The licensees or any person who has an interest adversely affected by this order may request a hearing within 30 days of the date of publication of this order in the FEDERAL REGISTER. A request for hearing must be addressed to the Director, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with copies to the Assistant General Counsel for Enforcement at the same address. If a person other than the licensees requests a hearing, that person shall set forth with particularity the manner in which the petitioner's interest is adversely affected by this order and should address the criteria set forth in 10 CFR 2.714(d).
If a hearing is requested, the Commission will issue an order designating the time and place of the hearing. If a hearing is held, the issue to be considered shall be whether this order should be sustained. Upon the failure to answer or request a hearing within the specified time, this order shall be final without further proceedings.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas E. Murley, Director Office of Nuclear Reactor Regulation Dated at Rockville, Maryland this 2nd day of January, 1990 Attachments:
- 1. SONGS 1 Cycle 11 FTOL Projects
- 2. SONGS I Cycle 12 FTOL Projects
- 3. SONGS 1 Operation Schedule
ATTACHMENT 1 SONGS 1 Cycle 11 FTOL Projects Item 1989 l
1990 1991 1992 1993 No.
Description A S1 N D J FM A MJJAD JF M A M J J
A S OND J
F M A M J J
A S 0 N DJ 61012/2 9/12 2M I
SEP III.3.A (Groundwater Leve) 12/
912 2
Classification of Stnsctures NRC 3
Reactor Coolant Pump SCE NrC Trip Removal 4
SEP III - 7.B (Bucking)
NRC Approval Ted Spec 5
RHR Over Pressure Protection Chwge NRCAprv 6
Reactor Vessel Embrittlement SCE Dimeas wth NRC PM I 7
ATWS - Salem NRC Approval 8
Reliol Valve Test SCE Resohne SER Issues
.Tes NFtC Final 9
ATWS (Diverse Twbine Trip)
Rest Appd Deskn I SCE Implemert Final I
I 10 Root Pondng (Scuppers)
Design I
SCE Implement Submb Final 11 480V Overload PCN Design SCE Implemen NFICApproval 12 Replace Charging Pc Install Motor Pump Motor SCE implemen w I
13 EO Hot Leg Recire.
I Finald 14 Component Cooling Water Dein SCE Permanent Fix 15 Rofueling Water Level ind Design
'Procue I
SCE Impleme A 16 RPS Testing INc Appmo PCNI 17 Prowdures Generation Padge SCE Submiitd NRC Approvd 10 Containment Venting NRC Apprmw PCN SCE Imlrment A SCE Action vr NRIC Action I
CYCLE 1I I
I CYCLE 12 I
I OUTAGE I
I OUTAGE I
- Critical NAC action required I
a n -
'fl'
ATTACHMENT 2 SONGS 1 Cycle 12 FTOL Projects Item 1989 I1990 I1991 I1992 I1993 No.
Decription
,A 1 1 0 1 N 01 J1 F M1 A M J J A S 0 N D IJ F IM A M J IJ I A ISI ONIDI~ 11F IM I A M, J1 J A1 SI ON iD J JF M
1212) 9/12 2/9 1
Simulator UnderRoview I
9 I
S i-2 Tornado Modfications UnderRoiew e
3 HELBA UnderReview odesoe I
I iknmcarm Modications 4
Containment Spray Testing NRC Appoe PCN S
Adequacy of Station Voltage SCE Submial INRC AWmvI I
I~Final DeskgVv SCE 5b Degraded Grid Voltage SCE Subnb PCN NRC Appovd Irriggemerd
- 6 TDI Diesel Crankshaft I
NRC Approvd 7
Station Blackout NRC Nericaion SCE issue Procedures 8
Seismic Adequacy of Peiom Plait 1.&Uodown Equipment (USI A-46) 1 Perfor P ki 9
Safety Parameter Display System SCE Srnaied NRC Approva Procure I
Iple"I A'
10 Sigle Failure Anlysis WCE sebmk Rewws R,eion of Rema'2 SEP ftDeinmsIplmr (Separation A hG 1.97) 11 Reg. Guide 1.97WESb"I NCAal (Non Single Faike) 12 Steam Generator OverfilNRC tn een SCE Sutnina NRC Approaln Mod (if
)A SCE 13 SIS/Recirc Upgrade NRc Approd Find Desiw~roowe Iplemen I I I
SCEI 14 Control Room Design Review g
NRC Approvd Find DesigroaI Implement 15 NUREG-0612 I
SCE Steel Plating asNRC Ap y Fnd Desiv E
SCECespanC SCESCE 16 Control Room Habitablity 00 PAS (I reD' Stal NRC ApvM Find DesigrvProare I
II CE 17 Synchrodeck Relay I
I k
,j 18 LCV 1100 B. CD Find Deskr Procure i mplent SCE 19 RVLIS/ Core Exit Thermocouples
.CE stw NM Approval SCE Subnittal NRC AMvFn DeskdProcure i kmpleent I
SCE 20 Waste Gas Decay Tank Find DesigrdProcur iple nt SCE 21 Inservice Test Modifications SCE Submindtt Final DesignrProcure ImpleenI I&SCE Action a
CYCLE II CYCLE12 7 NRC Action I
OUTAGE OUTAGE rrifical NRC action required 102M9
ATTACHMENT 3 SONGS 1 Operation Schedule 189 1990 I1991 199 SO0 N D J FM M
1 J
SON D '
M A MJ J A SO0 Dj 119 1993M ii 31 326 6/0 2P2 ori7 12/16
/
Previously Planned Cycle to 3
M 6M Cycle 10 1Cycle 11 Operation 0
Steam Generator Thermal Shield Cycle II Start Cycle 12 Inspection Repair Refueling Outage.
RVLIS and FTOL Mods Refueling Outage S30 12 2 June 30,1990 Cycl*11 Cycle1 0
Cycle 12 Cycle II Refueling Outage.
Cycle 12 Steam Generator Inspection, Refueling Outage.
Thermal Shield Repair.
RVLS and and FTOL Items (Figure 1)
Other F dOL items (Figure 2) 9/29/09