ML20148H060

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Summary of 871207 Meeting W/Util at Plant Site Re Recent Events at Facility,Control Room HVAC & Facility Readiness for Restart.Meeting Agenda & Viewgraphs Encl
ML20148H060
Person / Time
Site: Rancho Seco
Issue date: 12/14/1987
From: Miller L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML19341D829 List:
References
NUDOCS 8801270115
Download: ML20148H060 (12)


Text

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k UNITED STATES

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g NUCLEAR REGULATORY COMMISSION rs REGION V k

l 1450 MARIA LANE. SUITE 210 WA LNUT CREEK, CAllFORNIA 94596 December 14, 1987 MEMORANDUM FOR: DN 50-312 FROM:

L. Miller, Chief Reactor ProjectsSection II

SUBJECT:

MINUTES FOR THE DECEMBER 7, 1987 MEETING BETWEEN NRC AND SMUD REPRESENTATIVES TO DISCUSS RECENT EVENTS, CONTROL ROOM HVAC, AND SMUD READINESS FOR RESTART The following is a sumary of an informational meeting held on December 7,1987 at Rancho Seco with representatives of the Sacramento Municipal Utility District (SMUD). Messrs. Martin and Andognini were present.

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Mr. Martin opened the meeting by stating that recent events at Rancho Seco to be discussed at the meeting were not consistent with a sound operating perspective by SMUD.

SMUD then made a presentation related to four topics: essential HVAC system performance flaws, post accident monitoring system status, Transamerica Delaval diesel vibration problem status, and a critique of the lessons learned by SMUD in two recent spills. A copy of the material SMUD provided for the discussion is enclosed.

Concerning the essential HVAC system, SMUD acknowledged that an internal SMUD communications breakdown had been the reason why the system had not been operable for the November 9, 1987 NRC inspection of it, contrary to SMUD assurances that it would be operable. SMUD reaffirmed its intention to be certain that the system was operable before the next NRC visit. NRC staff questioned whether a complete flow balance of the system had been performed to ensure that the potential effect of any leakage paths had been quantified, and were assured that this had already been done.

SMUD also explained that the recent HVAC miswiring that SMUD discovered was still being investigated, but was at present partially explainable as a wiring error which was made during a recent system modification. The error was not caught until the equipment was tested. SMUD representatives agreed with NRC personnel present that SMUD's troubleshooting in this event was not clearly defined, resulting in some confusion about what repair personnel were authorized to do. Mr. Andognini agreed that the scope and definition of the limits of troubleshooting would be performed within a few days.

In addition, a root cause investigation of the event would follow the security investigation, in progress.

Finally, a recent urcommanded start of the system was due to an undiagnosed procedure error which energized control power to an essential HVAC compressor while compressor interlocks were in an abnormal status.

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SMUD then presented their critique of a 300 gallon spill of spent fuel pool water on November 27,1987, and a 1200 gallon spill on steam generator water on November 25, 1987. The steam generator spill was presented to be due to an operator's failure to follow clear instructions. The spent fuel spill was more disturbing in that it reportedly occurred due to operator failure to control a movement of radioactive water with an approved procedure. An erroneous valve Ifneup was not recognized, and the spill resulted.

Mr. Martin expressed concern that the operators involved in this event had not followed instructions in one instance, and had not recognized the need for a procedure to move radioactive water in the other instance. This was compered to earlier SMUD laxity with movement of radioactive water which had occurred prior to the plant shutdown.

It was also stressed that a time had been reached after nearly two years in this outage where better SMUD

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performance was needed, above and beyond the generally constructive attitude which had been demonstrated. SMUD representatives acknowledged the need for better performance, and described some additional measures that will be taken-to improve it: valve lineups will be reviewed in the field by an extra assistant shift supervisor, all operators will be briefed by senior SMUD 4

managers on the lessons learned from these spills, and valve lineups 1111 receive a three level review for accuracy.

SMUD then described recent system modifications to the post accident sampling system which they had made, and which it was expected would significantly improve the system capability.

NRC personnel reiterated the necessity for the system to operate prior to restart.

Finally, SMUD personnel described their recent efforts to understand the possible sources of their Transamerica Delaval diesel vibration problems.

It was noted that a second consultant would be brought in by SMUD to review the work of their prime contractor on this job. Mr. Cranston described the similarities and differences which he had observed among the Rancho Seco, River Bend, and Shoreham diesel generator installations.

The meeting was concluded with summary sta ements by Messrs.

tin and Andognini.

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. Miller, Chie

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eactor Projects ction II cc: Region V Rancho Seco Staff G. Holahan, NRR G. Knighton, NRR G. Kalman, NRR R. Bevan, NRR l

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COMPRESSOR TRIP a

MISWIRING FLOW BALANCE CALCUl.ATION o

PASS UPDATE o

TDI UPDATE o

SPILLS REVIEW OF LAST 2 SPILLS LESSONS LEARNED CORRECTIVE ACTIONS / RECURRENCE PREVENTION

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Flow Balance Calculation o

Current Status Preparations for NRC Return Inspection 12/14/87 o

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GENERAL Many problem areas and issues relating to the acceptable operation of PASS have been resolved.

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System Degassing Process Concern - Mence alternate design o

o Alternate design mock-up produced excellent results o

Decision to implement System Summary o

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CHART REACTOR COOLANT EAERIA Method /Ecuin Remarks 1.

Chloride Ion Chromatography Assembled selected vendors L

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ALARA, simplicity Tested by STP 430 2.

Boron Ion Chromatography Assembled selected vendors (In-Line)

Special considerations -

ALARA, simplicity Tested by STP 430 1

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PH New Foxboro Instruments Small volume with good (In-Line) flow thru characteristics To be tested by STP 1131 4.

Conductivity New Foxboro Instruments Small volume with good (In-Line) flow thru characteristics To be tested by STP 1131 5.

Isotopic Multi Channel Analyzer Dilution aspects tested (In-Line) (Diluted) in STP 430 Identical to Hot Lab 6.

Total Gas Pressure / Temp Sensors Method similar to Hot Lab Volume Ratios except 2nd volume at (In-Line) atmospheric Senscr changed 7.

Oxygen GRAB Off site analysis

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CONTAINMENT ATMOSPHERE Sample Method /Eculo Remarks 1.

Isotiopic MCA - N2 Dilution Tested by STP 432 Obtain sample, Dilute

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Hydrogen H2 Monitors Routinely checked by S.P.

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12/1/87 1

TDI DIESEL BRIEFING

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-Problem Solving - Iterative Process (e.g., piping system tuning)

PR03LEMS SOLUTIONS 1.

Lube Oil Pump Discharge Line Pulsation Dampener Suction Air Removal Dot 2.

Jacket Water Return Lines Struts (Tuning by Support Relocation) 3.

Turbocharger tube Oil Drain Expansion loop 6

Root Cause - T01 Design of Engine Auxiliaries Engine Vibration versus Piping Vibration Pump Pressure Pulsations versus Piping Vibration Plan to Complete - Modify Design / Test Accettance Criteria - Fatigue Stress (Se7smic, Thermal, Dead neigrt, Interr.a Pres:tre acceo;6 tie)

- Code Reauirements

nter' ace with NRC Cor.!icence in Sciutions 20953

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