IR 05000275/1985013
| ML17083B609 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 06/04/1985 |
| From: | Cills M, Garcia E, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17083B608 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-TM 50-275-85-13, 50-323-85-13, NUDOCS 8506240402 | |
| Download: ML17083B609 (14) | |
Text
U. S.
NUCLEAR REGULATORY COMMISSION
REGION V
Report Nos.
50-275/85-13, 50-323/85-13 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:
Inspection at:
Diablo Canyon Units 1 and
San Luis Obispo County, California Inspection conducted:
April 15 through 19 and telephone conversations through April 26, 1985.
Inspectors:
E.
5. Garcia, Radiation Specialist Date Signed
~M. Cillis, Radiation Specialist Date Signed Approved By:
G.
P.
uha
, Chief Facilit'es Radiological Protection Section Da e Signed Summary:
Ins ection on A ril 15 throu h 19 and tele hone conversations throu h
A ril 2 1985'e ort Nos.
50-275 85-13 and 50-323 85-13 Areas Ins ected:
Routine unannounced inspection by regionally based inspectors including general employee radiation protection training; Unit 2 preoperational tests, radiation monitor calibrations, and implementation of NUREG-0737, Items II.B.3 and II.F.l; and plant tours.
This inspection involved 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> onsite by two inspectors.
Results:
Of the five areas inspected no violations or deviations were identified.
8506240402 850604 PDR ADOCK 05000275 G
DETAILS 1.
Persons Contacted a.
Pacific Gas and Electric Com an
~ J L.
'M
"T
'R W.
A.
A.
M.
L.
C. Thornberry, Plant Hanager V. Boots, Chemistry and Radiation Protection (CHIRP) Manager F.
Womack, Engineering Manager N. Norem, Lead Startup Engineer L. Grebel, Regulatory Compliance Supervisor Wogsland, Technical Assistant to Nuclear Power Operations (NPO)
Manager P.
Powers, Senior CHIRP Engineer Coley, Startup Engineer Dame, Senior Instructor, GET O. Taylor, CHIRP Engineer J. Taylor, CHIRP Engineer W. Stephens, IRC Maintenance Supervising Foreman T. Horetti, CHIRP Foreman b.
Contractors T. Hagen, Unit 2 Startup Engineer Group Supervisor (Bechtel)
N. Singh, Unit 2 Startup Engineer (Bechtel)
J.
Ryan, Unit 2 Startup Engineer (Bechtel)
H. H. Mendonca, Senior Resident Inspector M. L. Padovan, Resident Inspector T. J. Polich, Resident Inspector T.
M. Ross, Resident Inspector Indicates those individuals attending the exit interview on April 19, 1985.
In addition to the individuals noted above, the inspector interviewed other members of the licensee's and'ontractor's staff.
2.
General Em lo ee Radiation Protection Trainin (GERPT)
CFR 19.12, "Instruction to Workers," describes the instructions that must be provided to individuals frequenting the restricted area.
The inspector participated in several courses provided by the licensee.
These courses are:
SRD 100 DCPP Site General Rules and Regulations.
RPA 400 Radiation Protection for Unescorted Radiation Workers.
RPD 650 Site Specific Radiation Protection for Unescorted RCA (Radiation Control Area) Acces RPA 700 Radiation Protection for Escorted Access.
RPC 700 Contamination Control Procedures.
With the exception of RPC 700 the courses consisted mainly of lectures with handouts complementing the oral presentations, and two short video tapes'PC 700 included the actual donning and removal of contamination protection clothing.
The training involved approximately 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> over four days.
In conversations with the Senior Instructor and the Chemistry and Radiation Protection Manager (RPM) the inspector described specific areas for improvement.
The inspector was informed that the licensee's training and radiation protection staff would meet to discuss the inspector's observations for the purpose of improving the GERPT program.
The training as presented appeared to meet the requirements of 10 CFR 19.12.
During the exit interview the findings in this area were briefly discussed.
No violations or deviations were identified.
Prep erational Tests Inspection Report 50-323/85-04 listed those preoperational tests being tracked by the inspector.
During this inspection it was noted that the selected preoperational tests had been completed, approved, and accepted or that those not completed had been included in the Master Completion List.
Some of the test documentation was examined by the inspector.
The following, information is accurate as of April 18, 1985.
Except as noted below, the following tests were conducted in accordance with the applicable procedure and the acceptance criteria have been satisfied.
Test 1.9Al Containment Evacuation Alarms The test was approved by the Lead Startup Engineer on January 19, 1985, and accepted by the Plant Superintendent on February 20, 1985.
Test 11.1 Nuclear Steam Su l Sam lin S stem Flush The test was approved by the Lead Startup Engineer on January 19, 1985, and accepted by the Plant Superintendent on February 7,
1985.
Test 11.2 Nuclear Steam Su l Sam lin S stem Functional Test During a previous inspection the inspector had noted some inconsistencies in the records of this test (see Inspection Report 50-323/85-04).
The licensee had committed to repeat that portion of the test related to the Volume Control Tank.
The portion of the test related to the Volume Control Tank had been removed and was contained in a separate test, 11.2Al.
At the time of the inspection, test 11.2A1 had not been conducted but was included in the Master Completion List.
The procedure for test 11.2A1 included all the steps removed from the original procedure, however, the acceptance criteria has been amended.
The new acceptance criteria appeared to be acceptabl The original test, as amended, was conducted in accordance with the applicable procedure, and the acceptance criteria have been satisfied.
The test was approved by the Lead Startup Engineer on March 7, 1985, and was awaiting acceptance by the Plant Superintendent.
Test 11.4 Post LOCA Sam lin S stem Flush The test was awaiting approval by Lead Startup Engineer and acceptance by the Plant Superintendent.
Test 23.3 Auxiliar and Fuel Handlin Buildin Heatin Ventilation and Air Conditionin HVAC This test's field work is complete with the exception of a problem with high vibration (in excess of one inch/second)
on exhaust fan 2E-4 inboard and outboard bearings.
This test has not been signed by the responsible startup engineer nor has it been approved or accepted.
This test is included in the Master Completion List.
The installation and testing of the HEPA filters and charcoal adsorbers is not part of this test.
This test was originally done in 1978 under test 23.11, Charcoal and HEPA Filter Test.
With the additional construction work that has taken place since 1978 and the decision by the licensee to replace the HEPA filters, the new adsorbers and filters will have to be tested.
The licensee performs this test as a surveillance as required by Technical Specification 4.7.6.1.
These systems are not required until Mode 4, for the auxiliary building or when spent fuel is in the fuel handling building.
Although, the licensee is obligated to conduct these tests by the Technical Specification requirement, at the urging of the inspector the licensee added the test for the auxiliary building system to the Master Completion Lists Test 23.10 Containment H dro en Pur e
S stem The test was approved by the Lead Startup Engineer on April 9, 1985, and accepted by the Plant Superintendent on April 10, 1985.
Test 24.2R2 Gaseous Radwaste S stem The test was awaiting approval by Lead Startup Engineer and acceptance by the Plant Superintendents Test 38.4 Radia on Monitorin S stem The test was awaiting approval by Lead Startup Engineer and acceptance by the Plant Superintendent.
Test 38.4Al Radiation Monitors 2-RE-32 2-RE-33 and 2-RX-40 Sam le Line Heat Trace The test was approved by the Lead Startup Engineer on March 7, 1985.
The test was awaiting acceptance by the Plant Superintenden The status of the tests examined and the items included in the Master Completion List were discussed during the exit interview.
Based on the progress made in completing the selected tests and the inclusion in the Master Completion List of incomplete items, this followup item is consider closed.
(50-323/82-12-01, Closed)
No violations or deviations were identified.
Unit 2 Radiation Monitors Calibration 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."
The procedure includes area, process, effluent, NUREG-0737 Item II.F.1 accident monitors, and miscellaneous monitors.
Isotopic calibrations are not part of this procedure, these calibrations are performed by the NPO ISC department.
At the time of the inspection, the test field work had been completed and the monitors had been released to NPO ISC department for calibration.
The calibrations of those monitors required in the proposed Technical Specifications had been completed by the end of the inspection on April 25, 1985.
The records of the calibrations of monitors RE-23, Steam Generator Blowdown Tank Discharge, and RE-30 and RE-31, Containment High Range Area monitors were examined.
It was noted that the calibrations had been performed in accordance with the applicable procedure and the acceptance criteria were met.
The inspectors also observed part of the calibration of monitors RE-32, Plant Vent Iodine Mid Range, and RE-33, Plant Vent Noble Gas Mid Range.
It was noted that the appropriate approved procedure was available and was being followed.
Section 11.4.4.3 of the Updated Final Safety Analysis Report (UFSAR)
titled "Calibration Procedures" states in part "Area and process monitors were initially calibrated by their original manufacturer.
Response curves for each detector were provided with the instrument.
These curves essentially relate detector performance to the energy spectrum that the detector would see in operation."
During the previous inspection (Inspection Report Number 50-323/85-07)
the inspector had requested that the licensee locate the records of the initial calibrations performed by the original manufacturer.
During this inspection, the licensee made this information available, and the inspector examined selected portions of these records.
'The inspector noted the information kept by the licensee is consistent with the description in the UFSAR.
In discussions with the Technical Assistant to the NPO Manager and during the exit interview, the licensee stated that they intended to have all Technical Specification required radiation monitors calibrated and declared operational prior to fuel load; however, if some unforeseen circumstance prevented this task being completed by that deadline, the individual monitors would be added to the Master Completion List.
In a telephone conversation on April 25, 1985, the ISC Supervising Foreman informed the inspector that all Technical Specification required radiation monitors had been calibrated and declared operable.
The licensee has installed, calibrated and made operational the Technical
i
Specification required radiation monitors for Unit 2.
The inspector has no further questions on this matter and this item is consider closed.
(50-323/81-05-02, Closed)
No violations or deviations were identified, 5.
Unit 2 Im lementation of NUREG-0737 Items II.B.3 and II.F.l Previous inspections have examined the licensee's progress in implementing their commitments as they relate to NUREG-0737 Items II.B.3,
"Post Accident Sampling System (PASS),"
and II.F.1, "Additional Accident Monitoring Instrumentation,"
Attachments 1, 2, and 3 (see Inspection Report Nos. 50-323/84-29, 59-323/84-24, 50-323/84-19, 50-323/85-04, and 50-323/85-07).
a.
Item II.B.3
"Post Accident Sam lin S stem (PASS)"
The reperformance of preoperational test 11.5, "Post LOCA Sampling System" has been completed.
The NPO staff independently performed procedure STP G-14, "Operability Determination of Post Accident Sampling Program."
The inspector examined records of preoperational test 11.5.
This review indicates that the test was conducted in accordance with the applicable procedure, and that the acceptance criteria were met.
Review of the data from the NPO performed STP G-14 indicate that individual components of the system are operable and that the licensee can collect and analyze the required samples using this system.
At the end of the site visit the only remaining items for the licensee to declare this system operable were completion of the heat tracing of the containment atmosphere sample line and completion of the calibration of the mid-range iodine sampler/monitor, RE-32.
In a telephone conversation on April 25, 1985, the responsible engineer informed the inspector that the two remaining items had been completed and the system had been declared operable.
The inspector noted that training on the use of the PASS has been provided, procedures have been implemented, and the equipment is installed and being maintained.
The inspector concluded that the licensee has met their commitment to this requirement as it relates to Unit 2.
b.
Item II.F.l Attachments
2 and
The monitors and samplers associated with Item II.F.1 are included in preoperational test procedure 38.4 with other radiation monitors.
All of the instruments have been released to NPO I&C for isotopic calibration.
By the end of the inspection, on April 26, all of the monitors had been calibrated and declared operable.
The inspector examined the records for the calibrations of monitors RE-30 and RE-31, Containment High Range Area Monitors. It was noted that the calibrations had been performed in accordance with the applicable procedure and the acceptance criteria were met
~
As noted in Paragraph 4 above, the inspector observed portions of the calibrations of monitors RE-32, Plant Vent Iodine Mid Range, and
r
RE-33 Plant Vent Noble Gas Hid Range.
It was noted that the appropriate approved procedure was available and was being followed.
The licensee had installed the monitors and samplers to which they committed in their response to NUREG-0737 Item II.F.l, Attachments 1,
2 and 3.
The instruments have been calibrated and declared operable.
Procedures for use and maintenance have been established.
These procedures are the same as those used for the Unit 1 monitors.
Personnel have been trained in the use of these instruments:
The inspector concluded that the licensee has met their commitment to this requirement as it relates to Unit 2.
The licensee was informed of the inspector's conclusions during the exit interview.
This item is consider closed.
(50-323/83-26-01, Closed)
No violations or deviations were identified.
6.
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'adiation labels as measured with NRC's instrument were comparable to those measurements made by the licensee with their instrument, and noted in recent radiation surveys.
The inspector used a Eberline R0-2 Ion Chamber serial number 837 calibrated on February 15, 1985.
Personnel observed in the control area used appropriate dosimetry as required by radiation work permits.
No violations or deviations were identified in this area.
7.
Exit Interview At the conclusion of the inspection the inspector met with the individuals denoted in Paragraph 1.
The'cope and findings of the inspection were presented.
Specific areas discussed are described in Paragraphs 2, 3, 4, 5.
The licensee was informed that no violations were identified.