IR 05000312/1983017
| ML20024C324 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 06/17/1983 |
| From: | Canter H, Obrein J, Obrien J, Thomas Young NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20024C314 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.3, TASK-1.C.1, TASK-2.D.3, TASK-TM 50-312-83-17, NUDOCS 8307120519 | |
| Download: ML20024C324 (15) | |
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OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
Report No. 50-312/83-17
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Docket No. 50-312 License No. DPR-54 Safeguards Group
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Licensee: Sacramento Municipal Utility District P. O. Box 15830 Sacramento, California 95813 Facility Name: Rancho Seco Unit 1
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Inspection at: Herald, California (Rancho Seco Site)
Inspectors:
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Ifarvey L. Can@ r, Sen rgkesid(ntInspector Date Signed C]
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&n 23 John O'Brien, (Dnit Rekdep6t In[pector Date Signed
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Approved by:
T. Young, Jr., pief Rebtp'r Projects Section 2, Date Signed Reactor Projects Branch No. 1
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Summary:
Inspection between April 30-June 8, 1983 (Report No. 50-312/83-17)
Areas Inspected:
Inspection during long-term shutdown; maintenance observations; surveillance observations; TMI modification follow-up; follow-up on Licensee Event Reports; Review of plant operations, follow-up on
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Enforcement Items; follow-up on Regional requests; media contacts and independent inspection effort. The inspection involved 214 inspector-hours performed by two resident inspectors.
- Results
- . Of the ten areas inspected, no items of noncompliance were
' identified.
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DETAILS 1.
- Persons Contacted R. Rodgriguez, Executive Director, Nuclear Operations 1-P. Oubre', Manager of Nuclear Operations
.2 D. Blachly,_ Operations Superintendent E. Bradley, Supervising Environmental Specialist N. Brock, Electrical /I&C Maintenance Supervisor Q. Coleman, Mechanical Engineer R. Colombo,' Technical Assistant R. Cordone, Emergency Planner 2 G. Coward, Maintenance Superintendent D. Cradle, EMD Mechanic, 1,2' S. ~ Crunk, Associate Nuclear Engineer 2 D. Elliott, Senior Quality Assurance Engineer 2 B. Fraser', Electrical Engineer D. Gardiner, Senior Chemical & Radiation Assistant J. Hutchensen, Allis-Chalmers Mechanical Engineer J. Jewett, Quality Assurance Engineer
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1,2 W. Jurkovich,_ Supervising Resident Construction Engineer
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F. Kellie, Assistant Chem. and Radiation Superintendent
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' l R. Lawrence, Mechanical Maintenance Supervisor 1 J.'McColligan, Principal Project Engineer
- 1-B.'Mquade, Quality Assurance Engineer
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1,2 R. Miller, Chemistry / Radiological Superintendent
l',2 :T.= Perry, o0n-site Quality Assurance Supervisor
' fJ. Price, Surveillance Test Coordinator
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2 S.1Redeker, S.T.A.: Supervisor
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- S.IRutter,, Quality' Assurance Director
';L'.-Schwieger, Quality Assurance Director
- B. ; Spencer, Shif t. Supervisor T.' Tucker, Plann'er/ Scheduler J. Uhl, Mechanical Engineer
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1:B.' White, Associate Electrical Engineer
'D.. Whitney, Engineering and Quality Control Superintendent
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B. Wichert, Plant Mechanical Engineer W.: Wilson, ; Senior Chemical & Radiation Assistant i
The inspectors also talked with interviewed several other licensee
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employees, including members of'the engineering, maintenance, operations and quality assurance (QA). organizations.
1 DenotesjthoseattendingtheExitInterviewon.May 18, 1983.
2 Denotes those attending' the Exit Interview on June 1,1983.
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Inspection During Long Term Shutdown During the report period, the inspectors observed control room operations, reviewed applicable logs, and conducted discussions with control. room operators. The inspectors verified surveillance tests required during the shutdown were accomplished, reviewed tagout records, and verified applicability of containment integrity. Tours of Auxiliary Building and Reactor Building accessible areas, including exterior areas were made to assess equipment conditions, plant conditions, radiological
. controls, safety and adherence to regulatory requirements and to verify that maintenance requests had been initiated for equipment in nee'd of maintenance. The inspectors observed plant housekeeping / cleanliness conditions, including potential fire hazards, and verified implementation of radiation protection controls. The inspectors by observation and direct interview verifieid that the physical security plan was being implemented in accordance with the station security plan. The inspectors reviewed the licensee's jumper / bypass controls to
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verify there were no conflicts with technical specifications and
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verified the implementation of radioactive waste system controls. The inspectors witnessed portions of the radioactive waste systems controls associated with radwaste shipments and barreling.
The plant has been in a major outage status during this report period.
The critical path items which must be completed on schedule in order to meet a July 31, 1983 on-line date include work on Hydrogen Monitors, the Interim Data Aquisition and Display software, the post Accident Sampling System, Nuclear Service Electrical Building fire protection and electrical systems, Main Steam Reheaters, Acid / Caustic modifications,
'and turbine-repairs.
A management change was announced during this report period in that
'Mr ' Pierre Oubre' has moved from Plant Superintendent to the Manager of Nuclear-Operations position, previously held by.Mr. Ron Rodriguez, the new Executive Director, Nuclear. The job announcement for the new Plant Superintendent closes on June 15, 1983. Also, the Plant Nuclear Engineer resigned during this. period and finally, the Operations
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Superintendent announced.his resignation, effective in August, 1983.
By the'end of.this report period all thermal shield and barrel bolts
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were in place. NRR has been kept informed of the bolt work, but has not closed out the issue.
1No items'of" noncompliance or deviations were identified.
3.
Maintenance Observations :
The inspectors observed portions'of the maintenance activities listed below and verified that work was' accomplished in accordance with approv,ed procedures, that work was accomplished by qualified personnel, that provisions for stationing a fire watch to oversee activities
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- involving welding'and open flame were complied with and that LCO requriements were met during repair.
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-Containment isolation valves for the Reactor Building Purge system
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(See comments Paragraph 6).
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~ b '. ' ','A"l Fuel. transfer -tube track repair.
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Letdown hea,t exchanger installation.
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Thermal shield and core barrel bolt installation and torquing operations.
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Diesel Generator: The inspector witnessed major tune-up work on the "A" diesel. An Electromotive Division (GE) representative was performing the work. He appeared to have extensive knowledge about
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-the equipment.he.was maintaining.
i No items of noncompliance or deviations were identified.
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4.
Surveillance Observations The inspectors O served' portions of the below listed surveillance testing to verify that the tests were covered by properly approved l
procedures; that the procedures.used were consistent with technical specification requirements; that' minimum crew requirements were met;
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.that' test prerequisites were~ completed; that special test equipment was
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calibrated and.in service; and, that the test results were adequate.
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- SP201.03B - (Motor Driven) P-440 - Fire pump operational test.
b.
-SP206.03A
"A" Diesel-generator surveillance test.
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SP212.01D -~ Sample / Analysis of breathing air.
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SP201.10B - Safety system Hydraulic Snubber Surveillance tests
(partial).
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. SP205.02 - Local Component leak rate test.of Reactor Building purge
valves.
No items of noncompliance or deviations were identified.
5.
-Three Mile-Island Modification Followup i
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Previous-inspection reports document various actions taken by the SMUD to comply with NUREG-0737, TMI Action Plan requirements.
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'This paragraph documents further activities performed by the inspectors
-in support of-the NRC verification activities.
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NUREG-0737 - Item I.A.1.3.2.A:
Minimum Shift Crew (Closed)
Generic. letter 82-33 states in effect that having four licensed operators per shift is to be thought of as guidance. The licensee is still pursuing 6-4 licensed operator crews by June, 1985, but,the inspectors review of this item is CLOSED because of the generic letter statement. This item could be reviewed in the future as the NRC inspection requirements dictate, b.
NUREG-0737 - Item I.C.1:
Short-term Accident & Procedures Review (0 pen)
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Paragraph *2.B. sad.3.B of this ' item are to be implemented as part of the ATOG (Abnormal Transient Operator Guidelines) procedure modifications. :The effort ~is currently scheduled for implementation during the next' refueling outage in 1985, so this review will be delayed until that time.,
KUREG-0737:
Item II.D.3.1 - Direct Indications of Valve Positions
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(Closed)
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All' actions necessary to meet the'rhquirements for this issue are
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now complete. Th'e charge converter.and cable problems mentioned in reports 50-312/81-12, 80-29, and 80-23 have been solved with the running of new cablestin the Reactor Building and the movement of the charge converter to the "TMI" panel in the Computer Room. This item is CLOSED.
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No items of noncompliance or deviations were disclosed.
6.
Licensee Event Report Follow-up (LER)
The resident inspectors performed an examination of the following LERs to ascertain whether additional inspection effort or other IE response is warranted, whether correcrive action discussed in the licensee's report appears appropriate, and whether the information reported to the NRC appears to satisfy reporting requirements.
In addition, the inspectors attempted to ascertain whether these events involved continued operation in violation of regulatory requirements or license conditions.
The LER's listed below appear to meet the above criteria and require a.
- no furtherffollowup at this time.
(1) 81-02-LO: Replacement of the "A" Letdown Cooler (Closed)
A new letdown cooler, to supplement the existing system was-des'igned and put in place during the last outage.
(Start of Cycle 5).The inspector witnessed the final tie into the existing system and reviewed the associated welding and maintenance procedures.
.This item is CLOSED.
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'(2) 83-07-LO:
"D" RPS Underpower Relay Failure for "C
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Reactor Coolant Pump (Closed)
See' discussion under LER 83-17-LO.
This item is CLOSED.
'(3)~'83-13-LO:
Reactor Building Purge Filter Failure (Closed)
The inspector reviewed the procurement documents and completed
' surveillance tests and verified the licensee took the appropriate corrective action prior to refueling operations.
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This item is' CLOSED.
(4) 83-14-TO: Failed Local Leak Rate Tests of'the Reactor Building Purge-Valves (Closed)
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'This' item was addressed in Paragraphs 3 and 12 of Region V inspection Report No. 50-312/83-10. Since that time, the licensee has been visited by an Allis-Chalmers representative..He verified that the licensee had taken proper corrective action, and recommended that increased preventative maintenance be performed on the air operating
- cylinders. The resident inspector interviewed the representative and found him to be experienced and-knowledgeable concerning operations, and maintenance of these valves. The vendor representative was also aware of the NRC concerns dealing with the operation'of.the valves during post
'LOCA conditions. The Resident Inspectors have reviewed the -
preventative maintenance' schedule, machinery history and
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surveillance history of these valves. The licensee has increased the priority of the preventive' maintenance of the-air operators. and had committed to increasing the frequency
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This item is" CLOSED.
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..D f(5)p83-12-LO:~iMissed Snubber Surveillance Test, and 83-16-LO,
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\\ gj<e Snubber Surveillance Test Failures (Closed)
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.Ihe lic'e.nsee is presently performing an extensive inspection
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- y-e and; maintenance program.for the, safety-related hydraulic
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- , 7 snubber' systems; The Bergen-Patterson vendor'has provided an
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7 mproved valve body nd poppet seat, and the' licensee is-i a
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<reworkingethe affected snubbers. 'The Resident' Inspectors'have
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, maintenance procedures and the
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surveillance test _ documents (SP201.10B). Thelinspectors have
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. verified the licensee has taken adequate' corrective action for
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,those snubbersLthat have failed.
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1ThisLitem is-CLOSED.
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b/ ~ The'LER'sjlistedbelowdonotmeettheabovecriteriaandrequire further-followup action by:the licensee.
(1) 79-21-L2: Feedwater Nozzle Replacement (Open)
The licensee has decided to continue through Cycle 6 with the same feedwater nozzles.as last cycle. Replacement has been
' delayed-due to procurement delays, but the licensee intends to replace the nozzles during the next cycle's refueling outage.
The present Preventative Maintenance program will be used to maintain the quality of the in place nozzles. The followup to lthis report will remain OPEN pending modification of the current; nozzles.
(2) 83-17-LO: Failure of Phase Balance and Underpower Relays (Open)
The licensee's Nuclear Engineering department has a person assigned to look into redesign or replacement of the relays.
This work is receiving a low priority due to the current refueling outage effects on resources. A licensee representative stated that these relays are "one-of-a-kind" and a fair amount of engineering may be necessary for replacement. This representative stated that a priority will be set after the current refueling outage to followup possible redesign or other corrective action.
In the meantime, the licensee is pursing a method to better test the " Auxiliary Feed Pump start on loss of Reactor Coolant Pump" circuitry (Technical Specification 48a in Table 4.1-1).
This circuitry depends on the proper operation of the aforementioned relays. The circuit cannot be tested at power,
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so one option of the licensee is considering is to incorporate the. test into Surveillance Procedure SP210.01F,
" Cold Shutdown Auxiliary Feedwater Pump Flow Test and Check Valve Full Stroke Test."
If that cannot'be arranged, they will write a new Surveillance ' Procedure to cover the test. An engineer started work on these options on June 6, 1983.
' Udtill further action is completed by the licensee this item will remain OPEN.
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lNoitemsofnoncomplianceordeviationswereidentified.
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7.
Review of Plant Operations The inspector attended, as an observer, a Plant Review Committee (PRC)
meeting on May 26, 1983. The membership and meeting frequency met technical specification 6.5.1 requirements. The subject of the meeting
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was whether or not a problem found on Woodward Governors (EG-B13C) was to be reported as a Part 21 report. The PRC decided that the Quality Assurance organization should report it via Part 21.
The inspector verified that a Part 21 Report was issued on May 27, 1983.
The problem is a possible generic one.
The " pointer disc" behind the
" speed setting adjustment control knob" can contact the " dial plate" and cause the diesel to " hang-up" at some speed less than full speed during a diesel start sequence. This can occur because the pointer disc and dial plate are in the same plane. This problem has occurred twice at Rancho Seco. The first occurence in 1981 was due to improper maintenance techniques. At that time, adequate corrective action was taken, but the generic aspects were not pursued by the licensee.
While performing a surveillance on a diesel generator with a newly j
overhauled EG-B13C governor in May, 1983, the operators noted that the diesel speed hung-up at about 650 rpm.
Upon investigation it was determined that the clearnace was too small between the pointer disc and dial plate. For corrective action, the licensee machined 1/16 inch off
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l the pointer disc, just as they did af ter the 1981 event. Retests were
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satisfactory on all three EG-B13C governors onsite. Also, as mentioned above, the licensee submitted a Part 21 Report and informed the industry of the problem via NOTEPAD, a computer operated industry-wide information system.
No items of noncompliance or deviaitons were identified.
8.
Follow-up on Items of Noncompliance The inspectors ascertained that the licensees responses for the following items of noncompliance are in conformance with regulatory requirements and that corrective actions are complete.
In this inspection effort, particular emphasis has been placed in the examination of the measures taken to correct the item and avoid further items of noncompliance. The corrective action should also have been taken in a timely manner. For the items listed below, the licensee's responses are satisfactory, such that the inspector's review is CLOSED.
a.
Items 82-08-01:
Civil Penalty for Two Level III Violations on Safety Related Components Inoperability (Closed)
It.is noted that during the current refueling outage, the white indicating lights were installed to indicate the physical status of the d-c charging springs on important breakers. Therefore, the corrective actions described in letters to the NRC dated July 12, l
1982; August 31, 1982, Spetember 3, 1982; November 23, 1982;
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November 29, 1982; December 17, 1982; and February 18, 1983 satisfy the criteria mentioned above.
This item is Closed.
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Item 82-38-01:
Logging of Events-(Closed)
The licensee's response dated December 15, 1982 adequately addresses corrective action. The corrective actions have been verified as complete. This review is CLOSED.
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Follow-up on Regional Requests During the inspection period,' personnel from the Region V office of the NRC in Walnut Creek, California, requested information from the. Resident Inspectors regarding the operation and maintenance of the Rancho Seco power plant.
Information was obtained and transmitted to the Region V concerning:
a.
Respiratory protection issues.
b.
Coalinga Earthquake: The May 4, 1983 earthquake was felt in the
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Control Room. The plant was shutdown and the fuel was in the spent fuel pool at the time of the quake. The seismic sensors which range from a horizonatal deflection of.005g to.25g were not tripped due to the earthquake. No plant problems developed as a result.
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Special Report 83-01.
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Core Barrel Bolt replacements.
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Emergency planning.
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Welder qualifications.
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Welding quality.
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' Drug usuage'onsite.
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Licensee Event Reports 83-07 and 83-17 (See Paragraph 6)
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Leakage through the concrete walls of the
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- Spent
- Fuel-Pool Leakage:
Spent Fuel-Pool occurred this month. The spent fuel pool liner
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,4 leakage collection system normally, drains to the Reactor Coolant
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System Drain Tank.(RCDT). The amount of leakage is not easily
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Lquantifiable. The licensee-has stated to the inspector that the
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ispent fu'el' pool liner has ybeen known to leak since about 1970' or,
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1971, prior to plant licensing. The inspector asked the licensee
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during;the May 18, 1983 exit for information on past leakage, present leakage, past reports and/or past -information on this
' problem such that a determination-of the seriousness of the leakage can be' determined. The licensee stated.that every time ~the collection. system drain line to the RCDT has been secured over the j
C' years, borated water.has leaked through spent fuel. pool welds and
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backed up beteween the spent fuel pool stainless steel liner and the concrete support structure. This acidic water then leaks through construction joints in the concrete and out of the west and east walls to'the environment. The leakage through the walls appears as wetted concrete. A white Boron crystal residue forms. On the west wall, the leakage appears on the grade, level of the turbine building, just north of the diesel rooms. The licensee covered this area,with; sheet plasticjso that per'sonnel would not rub against the boron cyrstals. The contamination was at a maximum of 2000 dpm.
The leakage appears more extensive on the east side of the building.
This leakage was not' covered with plastic because the east side of the building is in a radiologically controlled area or is not easily accessible. ~ The contamination levels on this: side were also about 2000 dpm and'not a serious radiological problem.
The licensee will take some corrective action on this issue. They will:
1.
Pursue diverting leaked water to soue other collection system in the future, rather than allow the water to back up in the annulus.
2.
Pursue past documentation of the problem in an attempt to address the USAR discussion of the spent fuel pool liner being leak-tight.
It is possible that a safety analysis of this problem has been completed which mitigates the problem.
3.
Install a flow meter in the drain line to the RCDT so that the amount of leakage can be quantified and increases in leakage can be detected.
(ECN 3196)
As part of the spent fuel pool re-racking which will commence in October, 1983, the licensee will inspect 100% of all spent fuel pool welds. Leaks will be patched.
The intent of these corrective actions is to reduce the physical and/or chemical stress on the re-inforcement bar inside the concrete walls and the walls themselves. This item will remain an Unresolved Item pending action on the above commitments.
(83-17-01).
No items of noncompliance or deviations were identified.
10. ' Media Contacts During the months of May and June, 1983, the inspectors communicated with the following' organizations and/or persons on items of interest with
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respect to Rancho Seco operations:
a.
Channel 3 - Mr. Tom DuHain b.
Channel 4 - San Francisco, Mr. Don Fields c.
. Sacramento Bee - Mr. Ted Bell d.
San Francisco Examiner - Mr. Fran Ortiz r
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Sacramento Bee - Mr. Ted Bell
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' San Francisco Examiner - Mr. Fran Ortiz
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San Fransisco, Examiner - Mr. Tim Reiterman
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, 11. ' Indepen' dent Inspection-Effort.
jDiscussionsIwereheldbetweentheResidentInspectorsandoperations
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security:and maintenance. personnel in an attempt to better understand
. *problessithey may have which are related to nuclear safety. These
'd,iscussions will continue'as a standard practice.
On nundro~us' occasions, during the inspection period, the Resident
= Inspectors attended shutdown status meetings. These meetings are held by l
the Plant Management to provide all disciplines onsite with an update on
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the plant status'and ongoing maintenance work.
9,
'In addition to the above, - independent inspection effort was performed on the following items:
a.
Core support assembly inspection (re:
ISI and the search for HPI thermal sleeve parts).
b.
Nuclear Service Electric Building and Diesel Building construction.
c.
Management controls of turbine deck work.
d.
Security computer problems and modifications.
Hot License Training (Attended a lecture on thermodynamics).
e.
f.
Item 80-23-02 on Safety Valve and Power Operated Relief Valve
~ indication in the control room is CLOSED.
Corrective action is adequate. See TMI Modification Section of this report under NUREG-0737 item II.D.3.1.
g.
Item 82-04-01 on High Pressure Injection and Make-up Pump Lube Oil Cooler replacement is CLOSED.
Stainless steel coolers are onsite and will be installed prior to startup from the current refueling
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outage.
h'. _ Item 82-25-01 on implementation of a computer operated software training records system will remain OPEN until a.secheduled implementation in September, 1983. The delay from July, 1983, is due.to the priority set'on this program by plant management.
Instrument and Control personnel are being utilized on higher priority items and hence, the work on this sytem has been delayed.
This computer software system is also being used to upgrade the plant security system..The hardware system is installed.
No it$ms of noncompliance or deviations were identified.
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12. ' Unresolved Items
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Unresolved items are matters about which more information is required in
order to ascertain whether they are acceptable items, items of g..,
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'. noncompliance,- or deviations. - An unresolved item disclosed during the
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. inspection is discussed in Paragraph 9.
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Exit Intervi::w
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cThe inspector me'd with licensee representatives (denoted in Paragraph 1)
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1983,fand summarized the scope and findings of the inspection activities.
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The' inspector informed.the licensee that other than Three Mile Island related commitments, the only NRR related " hold items". for startup deal
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>with'the missing thermal sleeve from the Make-Up nozzle and the status
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a "N INSPECTOR'S REPORT
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Draft Report 50-312/83-17 April 30 to June 8, 1983 tlours:
PPI & PRI :
214 PAP :
DOC :
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