IR 05000275/1985002
| ML17083B509 | |
| Person / Time | |
|---|---|
| Site: | 03010228, Diablo Canyon |
| Issue date: | 02/11/1985 |
| From: | Garcia E, Grayson W, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17083B508 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-TM 50-275-85-02, 50-275-85-2, 50-275-85-4, 50-323-85-04, 50-323-85-4, NUDOCS 8502280661 | |
| Download: ML17083B509 (18) | |
Text
U. S.
NUCLEAR REGULATORY COMMISSION
REGION V
e.ee, Report Nos:
50-275/85-02, 50-323/85-04 Docket Nos:
50-275, 50"323 License Nos.
DPR-80, CPPR-69 Licensee:
Pacific Gas and Electric Company 77 Beale Street Room 1435 San Francisco, California 94106 Facility Name: Diablo Canyon Units 1 and
Inspection at:
San Luis Obispo County, California Inspection conducted:
January 15 through 18, 1985 Inspectors:
M. Grayson, Ra ation Specialist Dat Signed.
E.
M. Garcia, Radiation Specialist
/Z Is Date Signed Approved by:
G P G.
P.
Y as, Chief, Facilities Radiological Protection Section Date Signed Summary:
Ins ection on Janua 15 throu h 18 1985 (Re ort Nos. 50-275/85-02 and 50-323/85-04 Areas Ins ected:,.
Routine unannounced inspection by regionally based inspectors-including radioactive waste disposal records; Unit 1 biological shield'radiation survey; Unit 2 preoperational tests, radiation monitor calibrationi, and impTementation of NUREG-0737, Items II.B.3 and II.F.1; followup on'radiation contamination incidents; followup on resolution of audit findings; and plant tours.
This inspection involved 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> on site by two inspectors.
Results:
Of the eight areas inspected no violations or deviations were identified.
8502280661 850212 PDR ADOCK 05000275 G
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DETAILS 1.
Persons.C6ntacted
'I a.
Pacifi'c Gas and Electric Com an-R.
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D.
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C. Thornberry, Plant Manager Patterson, Plant Superintendent V. Boots, Chemistry and Radiation Protection (CMP) Manager N. Norem, Lead Startup Engineer T. Murphy, Regulatory Compliance Supervisor A. O'ara, Senior CQP Engineer P.
Powers, Senior CHIRP Engineer P. Paranjape, Instrument and Control (ISC) Maintenance Engineer D. Pryor, ISC Maintenance Engineer J.
Angus, Reactor Engineer W. Stephens, ISC Maintenance Supervising Foreman A. Fergurson, C&RP Foreman H. Norton, IGC Maintenance Foreman b.
Contractor's D. Harris, Unit 2 Startup Supervisor (Bechtel)
A. Sears, Unit 2 Startup Engineer Group Supervisor (Bechtel)
T. Hagen, Unit 2 Startup Engineer Group Supervisor (Bechtel)
N. Singh, Unit 2 Startup Engineer (Bechtel)
A, L. Rogado, Unit 2 Startup Engineer (Bechtel)
c.
NRC Resident Ins ectors-M. M. Mendonca, Senior Resident Inspector T.
M. Ross, Resident Inspector
- Indicates those individuals attending the exit interview on January 18, 1985.
In addition to the individuals noted above, the inspector interviewed other members of the licensee's and contractor's staff.
2 ~
Radioactive Waste Dis osal Records As part".of. an inspection of the licensee's by-product material license No. 04-08134-03, a review of inventory and disposal records was conducted~.
-During this review inconsistencies were noted in licensee recoids"of the contents of radioactive waste drum No. 84-0001, which contains small unusuable sources.
Discussions with licensee representatives indicate that several small liquid sources may not be contained in the drum. It appears that these sources were actually disposed to the sink in the counting room.
The sink drains to the radioactive waste treatment system.
This drum has not been shipped offsite for disposal'he licensee is evaluating the cause of apparent discrepancies.
The licensee's resolution of this matter will be reviewed in a future inspection.
(50-275/85-02-01, Open)
Unit 1 Biolo ical Shield Radiation Surve I
The licensee is. conducting radiation surveys to determine biological shieldgag; effectiveness.
These surveys are part of startup test No. 1.15'; and.are controlled by temporary procedure TC-8401 "Biological Shield Survey for DCPP Unit 1."
The procedure and data collected at lower power plateaus has been examined and found acceptable (see Inspection Reports 50-275/84-41, and 50-275/84-15).
The inspector reviewed the survey data collected at the 50$ power plateau.
The records indicate that the survey was conducted as directed by the procedure.
No significant problems with shielding effectiveness have been identified.
Neutron dose equivalent exposures rates have been lower than expected.
Further surveys will be conducted at 75/,
90$, and 100$ power plateaus.
A contractor is scheduled to collect neutron energy spectrums during the 75/ power plateau.
(50-275/84-37-01, Open)
No violations or deviations were identified.
Unit 2 Prep erational Tests Inspection Report 50-323/84-29 listed those preoperational tests being tracked by the inspector.
Figure 1 (attached)
describes the status of,-
the selected tests using the licensee's accounting methodology.
No additional tests had received final acceptance by the licensee.
Four additional tests had been completed and signed by the responsible startup engineer.
The licensee has deleted startup test procedure 1.9A2, "Public Address System Test."
According to the startup supervisor this test was deleted because this system will be tested by the Communications group and testing by the Startup group will only be repetitive.
Since this test is not listed in the Updated Final Safety Analysis Report (UFSAR), and operability of this system will be determined by another group, deletion of this test is acceptable.
Records of tests 11.2 and 23.3 were reviewed by the inspector.
This review indicates 'that test 23.3, "Auxiliary and Fuel Handling Building HVAC Preoperational Test,"
was conducted by the applicable procedure, and that the acceptance criteria were met.
The operability of the HEPA'ilters and charcoal absorber bank, as defined in Technical Specification 4.7.6.1, was not.demonstrated by this test, nor had they been demonstrated by"other tests.
The operability of this air filtration system."will be demonstrated by the NPO Engineering Department.
The responsible-engineer stated that this requirement will be met prior to fuel load.
The inspector identified the following two inconsistencies in the records of test 11.2, "Nuclear Steam Supply Sampling System Functional":
1)
Test steps 6.5.1.2 through 6.5.2.8 were recorded as being performed before the test was initiated.
2)
Test procedure change 4 changed the acceptable sample flow on step 6.8.2.2 and 6.8.2.4 (inlet samples from demineralizers to
Volume Control Tank and miscellaneous equipment drain tank).
The recorded flows on Data Sheet 2 did not meet the new criteria.
,These. matters were brought to the attention of the responsible Startup Engineer.
He stated that the inconsistencies were due to personnel error and that a test procedure change was being issued to correct the errors.
Review by the inspector of the new test=procedure change identified that as a results of this lattest change another inconsistency was created.
This inconsistency was between the flow criteria in step 6.8.3.3 and that recorded in the Data Sheet.
At the exit interview, the Lead Startup Engineer stated that the portion of test 11.2 related to the Volume Control Tank would be repeated.
Tests 11.2 and 23.2 had not yet been approved by the Lead Startup Engineer and accepted for operation by the Plant Superintendent.
The licensee's actions on these two tests and the remaining selected tests will be examined in a future inspection.
(50-323/82-12-01, Open)
No violations or deviations were identified in this area.
5.
Unit 2 Radiation Monitors Calibrations Previous inspection reports have examined the status of installation and calibration of radiation monitors.
The applicable preoperational test procedure is 38.4 "Radiation Monitoring System."
This procedure is 66/
completed.
The procedure includes area, process, effluent, NUREG-0737 Item II.F.l accident monitors, and miscellaneous monitors.
Isotopic calibrations are not part of this procedure, these calibrations are performed by the NPO IRC department.
At the time of the inspection, the following monitors had been released for calibration by the Startup group and had been calibrated by the NPO IRC department:
TYPE NUMBER DESCRIPTION Area Area Area Area Aiea.,
Ba'as,'as" Iodine Area Area Air Particulate Air Particulate Gas Gas RE-2 RE-4 RE-5 RE-6 RE-7 RE"9 RE" 14A RE-14B RE-24 RE-25 RE-26 RE-28A RE-28B RE-53 RE-54 Containment Low Range Charging Pump Room Spent Fuel Pool Nuclear Steam Supply Sampling Room Incore Seal Table Room New Fuel Storage Plant Vent Radioactive Gas Plant Vent Radioactive Gas Backup Plant Vent Iodine Control Room Ventilation Intake Control Room Ventilation Intake Plant Vent Air Particulate Plant.Vent Air Particulate Backup Control Room Pressurization System Control Room Pressurization System
The portion, of test 38.4 associated with the following monitors has been completed and these monitors have been released to NPO for calibration, but, the" ca1ibration has not been completed:
~.t TYPE, NUNBER DESCRIPTION Air Particulate Gas Liquid Liquid Iodine Gas Area Area Iodine Gas Area Area Gas Gas Gas Area Gas Gas Gas Gas RE-13 RE-15 RE-17A RE-17B RE"24 RE"29 RE-30 RE-31 RE-32 RE-33 RE-34 RE-35 RE-41 RE-42 RE-43 RE-48 RE-71 RE-72 RE-73 RE-74 RHR Exhaust Duct Air Particulate Condenser Air Ejector Component Cooling Water Header A
Component Cooling Water Header B
Plant Vent Iodine Normal Range Plant Vent High Radiation Gross Gamma Containment High Range Containment High Range Plant Vent Iodine Mid Range Plant Vent Noble Gas Mid Range Plant Vent ALARA Iodine Grab Sampler ALARA Gas Decay Tank 2-1 Gas Decay Tank 2-2 Gas Decay Tank 2-3 Sentry PASS ALARA Main Steam Line lead
The portion of test 38.4 associated with the following monitors has not been completed:
NUMBER DESCRIPTION RE-11 RE-12 RE-16 RE-19 RE-22 RE-23 RE-27 RX-40 RE"58 RE-59 Containment Air Particulate Containment Gas Waste Transfer Pump Discharge Steam Generator Blowdown Monitor Gas Decay Tanks Discharge Steam Generator Blowdown Tank Discharge Steam Generator Blowdown Tank Vent Plant Vent Iodine Sampler High Range Fuel Handling Building Fuel Handling Building No violations or deviations were identified in this area.
Air Particulate Gas Liquid Liquid Gas Liquid Gas Iodine Area-
... A8ig.,
During'-'.Ch6 exit interview the licensee was reminded that this test is identified in Chapter 14 of the FSAR and it is to be completed prior to the issuance of the operating license.
Subsequent to the inspection the IRC Supervising Foreman informed the inspector that all Unit 2 radiation monitors calibrations are scheduled to be completed by March 28, 1985.
The licensee's progress with the radiation monitors of Unit 2 will continue to be examined in future inspections.
(50-323/81-05-02, Open)
6.
Unit 2 NUREG-0737 Items II.B.3 and II.F.1 Preyiolisjinsp'ections have examined the licensee's pro'gress in implementing;.th'eir commitments as they relate to NUREG-0737 Items II.B.3,
"Post",A'c'ci'dent Sampling System (PASS)",
and II.F.l, "Additional Accident Monitoring Instrumentation,"
Attachments 1, 2, and 3 (see Inspection Reports 50-323/84-29, 50-323/84-24, and 50-323/84-19).
During this inspection it was noted that the licensee has continued to make progress on Unit 2 PASS.
The preoperational test procedure 11.5,
"Post LOCA Sampling System," is 80$ completed.
This preoperational procedure incorporates the acceptance criteria that is present in NPO procedure STP G-14, "Operability Determination of Post Accident Sampling Program."
The responsible engineer stated that the system will be operable prior to fuel load.
The status and calibration of the monitors associated with Item II.F.1 are noted in Paragraph 5 above.
The licensee is including these instruments in preoperational test procedure 38.4 with other radiation monitors.
With the exception of RX-40, all of the instruments have been released to NPO ISC for isotopic calibration.
Following is a list of, designated instruments and associated commitment:
Attachment 1, Noble Ga's Effluent Monitors RE-29 RE-33 RE-71 RE"72 RE-73 RE-74 Plant Vent High Range Plant Vent Mid Range Main Steam Line lead-1 Main Steam Line lead-2 Main Steam Line lead-3 Main Steam Line lead-4 Attachment 2, Sampling And Analysis of Plant Effluents RE-32 aX-40 Plant Vent Particulate/Iodine Mid Range
~
Plant Vent Particulate/Iodine High Range Sampler Attachment 3, Containment High-Range Radiation Monitor RE-30 Containment High Range Area Monitor
'RE.-31",,'(,':-.
Containment High Range Area Monitor The;-li'censee',s
~ogress with their implementation of their commitments to
,NUREG."0)32-: will,continue to be examined in future inspections.
(50-323/
83-26-01, Open)
No violations or deviations were identified in this area.
7.
Followu on Radiation Contamination Incidents Several incidents of personnel 'and clothing contamination have occurred in the last few weeks.
Review of documents and discussions with the cognizant licensee staff indicate that these incidents have been minor in nature, of insignificant health and safety consequences, and in some
instances the result of naturally occurring radioactive materials outside of; the control of the licensee.
Three incidents, involving a total of five individuals, can be attributed to contamination with licensed radfoactiye materials.
The maximum contamination level observed in any of thes'e'='incidents was 0.005 microcuries/100 square centimeters on a leg of a pair of pants.
The licensee's investigation concluded that the first incident was the result of failure to follow procedures by the individuals involved.
The other two incidents resulted from inadvertent contact with contaminated water.
The licensee's corrective actions included counseling the individuals involved, posting informational signs, issuing a memorandum to all site personnel, and incorporating the lessons learned in future training.
Several other instances were identified were garments became contaminated even though the individuals had not come in contact with licensed radioactive materials.
Surveys conducted by the licensee identified the contaminants as being naturally occurring radioactive materials.
The presence of an atmospheric inversion in association with the concrete buildings and garments susceptible to build up of static electricity are believe to be responsible for these incidents.
The licensee's action has been to hold the contaminated garment and resurvey it in two hours; if the contamination has decayed away then the garment is returned to the individual, otherwise further evaluations are made.
The licensee's
. evaluations,'onclusions and corrective actions are reasonable and acceptable.
C No violations or deviations were identified in this area.
Followu on Resolution of Audit Findin s Inspection Report 50-275/84-41 identified that Open Item Report (OIR)
number 84-024 had not been promptly resolved.
This OIR had been issued by the equality Assurance (gA) department to the CSRP department as a
result of findings associated with Audit.number 84027P.
The OIR dealt with a lack of procedures to: verify the accuracy of data input to computer calculations; periodically correlate effluent monitor readings to actual values; and analyze replicate samples for intralaboratory gC checks.
By letter dated December 21, 1984, the C&RP department informed gC that the corrective actions for OIR-84-024 were completed.
The gA department informed CHIRP that the response had been received and that they intended to'.,verify completion and effectiveness of corrective actioaa-at the next schedule audit.
This followup item is considered closed+ (50'"275/84-41-01, Closed)
C4% I No violations or deviations were identified in this area.
Plant Tours The inspector toured the plant to observe the implementation of radiation protection requirements.
It was noted that radiation, contamination and high radiation areas were properly identified and posted.
Radiation levels as measured by the inspector were found to be consistent with those measured by the licensee in recent radiation surveys.
The inspector used a Eberline RO-2 Ion Chamber serial number 2694 calibrated
on December 10, 1984.
Personnel observed in the controlled area wore dosimetry as required by radiation work permits.
No violations or deviations were identified in this area.
10.
Exit Interview At the conclusion of the inspection the inspector met with the individuals denoted in Paragraph 1.
The scope and findings of the inspection were presented.
Specific areas discussed are described in Paragraphs 2, 4, 5, 6, and 7.
The licensee was informed that no violations were identifie TEST PROCEDURE '"" ""..
'UMBER
"-DESCRIPTION SELECTED UNIT 2 PREOPERATIONAL TESTS PROCEDURE TEST
$ OF WRITTEN TEST REVIEWED SYSTEM Zr APPROVED COMPLETED 6 ACCEPTED COMPLETED 1.6 1.9 1.9A1 RCS CHEMISTRY COMMUNICATIONS SYSTEM YES CONTAINMENT EVACUATION ALARMS NUCLEAR STEAM SUPPLY SAMPLING SYSTEM (NSSSS)
FLUSH YES PARTIAL PARTIAL NO NO NO NO
45
90 11.2 NSSSS FUNCTIONAL TEST YES PARTIAL NO
11.4 11.5 23.3 POST LOCA SAMPLING SYSTEM FLUSH POST LOCA SAMPLING SYSTEM PREOP AUXILIARYAND FUEL HANDLING BUILDING HVAC PREOP YES PARTIAL PARTIAL PARTIAL NO NO NO
80
23.10 CONTAINMENT H2 NO
24.2R2 GASEOUS RADWASTE SYSTEM PREOP PARTIAL NO
24.2Al 02 ANALYZERS PREOP NO
38.4 38.4Al 38.4A3 RADIATION MONITORING SYSTEM RADIATION MONITORS HEAT'RACF RAOXATI6N. MONITORS RE-58,59 YES NO PARTIAL NO NO NO NO
84 FIGURE
'$
0