IR 05000312/1986039
| ML20215E469 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/05/1986 |
| From: | Jim Melfi, Richards S, Willett D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20215E454 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.D.2, TASK-2.B.2, TASK-TM 50-312-86-39, NUDOCS 8612220323 | |
| Download: ML20215E469 (5) | |
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U' S. NUCLEAR REGULATORY COMMISSION i
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a REGION V-
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. Report No'
~ ~50-312/86-39
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Docket No.
-50-312-License No.
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Licensee:
1 Sacramento Municipal Utility District P. O. Box 18530 Sacramento, California 95813 Facility Name:
Rancho Seco Nuclear Generating Station Inspection at:
. Clay Station, California Inspection Conducted:
November 12-13, 1986 Inspectors:
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M. J. Willeft, Reactor Inspector Date Signed J
x n/ax-shka (4. Melfi,. Reactof Ipsf(>ector Date Signed
'A Proved by:
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S. Richards, Chief, Engineering Section Date Signed
. Summary:
Inspection on November 12-13, 1986 (Report No. 50-312/86-39)
Areas Inspected: Routine, unannounced safety inspection of TMI (NUREG-0737)
issues.
Inspection Procedure TI-2515-65 was covered.
Results:
In the one area inspected no violations or deviations were identified.
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- 4 DETAILS 1.
Personnel Contacted
- G. Coward, Deputy Restart Implementation Manager
- R. Colombo, Supervisor Licensing / Compliance
- J. Janus, Supervisor HVAC (MAC)
M. Nakao, Licensing Engineer (Bechtel)
R. Roller, Licensing engineer J. Delazinski, Licensing Supervisor
- F. Hauck, Compliance Engineer
- T. Carver,. Licensing Engineer
- D. Comstock, Operations Superintendent D. Cox, Engineer The inspector also held discussions with other licensee and contract personnel during the inspection. This included plant staff engineers, technicians, administrative,-and clerical assistants.
- Denotes those personnel attending the entrance interview November 13, 1986.
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2.
TMI Issues'(NUREG-0737)
The inspectors reviewed the licensee's implementation of select TMI requirements. This review consisted of an examination of documentation, on a sample basis, regarding design, licensee commitments, and implementation schedule and discussions with managers, supervisors and personnel in licensing and engineering. The following specifics document the implementation / verification for the TMI issues reviewed and identifies any remaining action for their completion:
II.B.2.2.B Shielding (Closed). This item requires licensees to perform a radiation and shielding-design review of the spaces around systems that may, as the result of an accident, contain radioactive materials. The design review should identify the location of vital areas and equipment, in which personnel occupancy may be limited.
Licensee's letter J. Mattimoe to D. Eisenhut, September, 10, 1982, stated that the final evaluation of post accident shielding requirements had been completed and the results indicate that no additional shielding was necessary.
NRR letter J. Stolz to R.
Rodriguez, August 25, 1983 concluded, in the enclosed Safety Evaluation Report, that the post accident shielding modifications, at Rancho Seco, met staff criteria for NUREG-0737, item II.B.2 and that this item was considered closed.
II.B.2.3 Environmental Qualification (Closed). This item requires licensees, as part of the radiation and shielding-design review, to review safety related equipment (inside and outside of containment)
that may be unduly degraded by radiation fields during post accident operation of these system a r-
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In May 1985 a special team inspection directed by NRR conducted an inspection-of the licensee's environmental qualification program.
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1The inspection team concluded ~(in inspection report 50-312/85-14)
that the " licensee has implemented a program to meet the requirements of.10 CFR 50.49."
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I.D.2.3 Safety Parameter Display System (SPDS) (Open). This item requires licensees to install a parameter display system that.will display a minimum set of parameters which define the safety status of the plant.(NUREG-0737). The important plant functions displayed shall include: (1) Reactivity Control, (2) Reactor Core Cooling and heat Removal from the Primary System, (3) Reactor Coolant System Integrity, (4) Radioactivity Control, and (5) Containment Integrity (NUREG-0696). The critical functions of the SPDS (Reg. Guide 1.97-Category-1 parameters) shall be provided during and following earthquakes and design basis events (NUREG-0696).
Letter G. RivenBank, NRR to R. Rodriguez, SMUD, July 27, 1984, ask the licensee to include the following parameters.
- Intermediate Range Neutron Flux
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y Power Range Neutron Flux
RCS Level i
Subcooling
Containment Sump Level
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Stack Radiation
Containment H Concentration
- Steamline Radiation
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Letter J. Mattimoe to G. Rivenbank, October 2, 1984, provides information on to the above eight parameters and upgrades to the SPDS Category-1 variables. This letter states that, for stack
radiation, the containment effluent radiation monitors only function i
during cold shutdown and the steamline radiation parameter is part of the Digital Radiation Monitoring System (DRMS) which is displayed
on the IDADS computer.
The licensees' September 30, 1985 letter, R. Rodriguez to H.
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Thompson NRR, identifies that the SPSD was functioning and displayed
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the Category 1 variables except for:
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Hot Leg Level
Reactor Vessel Level
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Compensated Pressurizer Level Condensate S'torage Tank Level
Additionally, this letter stated that the licensee has seismically qualified all' equipment except the CRTs and control panel cabling.
This letter also said that the licensee will modify SPDS (in cycle 9) to provide:
Full Redundancy (two channels)
'.1-E Power-(standby power)
Necessary Seismic Qualification (displays)
Indication of all Category 1 variables (Reg. Guide 1.97)
NOTE:. Reg. Guide 1.97, " Generally, Category 1 provides for full qualification, redundancy, and continuous real-time display and requires onsite (standby) power."
On September 29, an NRC NRR team audit'ed the Action Plan, Control Room Design, Review, the upgraded SPDS,.and Reg. Guide 1.97.
The results of this audit are not documented at this time and will be evaluated in the close out of this TMI item.
-Letter,J. Ward to F. Miraglia, November 12, 1986, identifies the
' licensee's commitments to accelerate the implementation of Reg. Guide
=1.97 variables'into the SPDS. The following is a status of implementation.
Variables to be implemented prior to restart in 1987:
Steam Generator Level
RCS Hot Leg Temperature
SPDS Upgrade to Class-1 Redundant Indication
Steam Generator Pressure
Pressurizer Level Density Comp.
Variables to be completed in cycle 8:
Coolant Inventory Neutron Flux RHR Heat Exchanger Outlet
Quench Tank Temperature
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Containment Atmosphere Temp.
Pressurizer Heater Status The TMI item for SPDS will be. closed out in a further inspection following implementation of the cycle 8 variables and evaluation of the September 29, 1986 audit results.
3.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on November 13, 1986. The scope and findings of the inspection,'which were discussed during the exit interview, are set forth in paragraph 2 of this report.
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