IR 05000275/1981005
| ML16340B661 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/03/1981 |
| From: | Book H, North H, Wenslawski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML16340B660 | List: |
| References | |
| 50-275-81-05, 50-275-81-5, 50-323-81-05, 50-323-81-5, NUDOCS 8104300103 | |
| Download: ML16340B661 (24) | |
Text
50-275/81-05 Report No 50-323/81-05 U.
S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION V
Docket No. 50-275 and 50-323 License No CPPR-39 5 CPPR-69 Safeguards Group Licensee:
Facili ty Name:
Pacific Gas and Electric Company P;
0.
Box 7442 San Francisco, California 94106 Diablo Canyon Unit 1 and
Inspection at:
Inspection conducted:
San Luis Obispo County, California March 9-13, 1981 Inspectors:
H.
S. North, Radiation Specialist ate Signed pproved by:
F.
A. Henslawski, Chief, Reactor Radiation Protection
,.. 4, g. 8A~""
H.
E.
Book, Chief, Radiological Safety Branch Da e Signed
+/~/ri
- Date Signed Summary:
Inspection on March 9-13,. 1981 (Re ort:No.50-'275/81-05:and 50-323/81-05
~A<<d:
di i
<nistered and conducted wlthsn t e C8RP organization.
CHIRP personnel are trained in the more generalized areas of security, first aid, safety, Emergency Plan actions, etc.,
in accordance with Administrative Procedure No. 8-2.
Procedure No. B-250 provides for individual evaluation with provisions for waivers based on prior experience and training, classroom training, practical skills, and procedure review seminars.
A course outline includes topic, estimated classroom lecture hours, reference texts and course content.
The topics and lecture hours, based on individual skills and experience, are as follows:
Nucl ear Technol ogy Plant Design and Operation Radiation Protection Chemistry Radiochemistry 20-40 hours classroom lecture 40-60 hours lecture 20-30 hours plant tour introductory course 25-35 hours lecture standards and procedures 30-45 hours lecture 40-70 hours lecture 40-60 hours lecture.
The original procedure has been amended to incorporate a retraining requirement, quarterly, with a complete cycle completed every two years except for emergency procedures for which annual retraining is require The C&RPT staff is evenly divided into two groups on the basis of qualifications pursuant to ANSI/ANS-18. 1-1971.
Nine of the staff have received the training required by Procedure No. B-250, but do not at present satisfy the experience requirements of the ANSI/ANS Standard in radiation protection.
Eight of the staff are qualified in radiation protection based on prior participation in military or civilian nuclear power programs.
This second group has a minimum of two years radiation protection experience but had not completed the training program described in procedure No. B-250.
The licensee estimated that the required training to be completed for this group totals less than 20 full days.
The licensee has taken advantage of past training opportunities with respect to the first group of C&RPTs, and plans to send six of them to Trojan for work exper ience during the scheduled May-June 1981 refueling outage.
Training and expeirience records.for eight randomly selected C&RPTs, two C&RP Foremen and three C&RP Engineers were examined.
No items of noncompliance were identified.
Radiation Protection - Instruments and E ui ment The licensee has added the following instruments and equipment:
12, Eberline Teletectors; 6, Eberline PRM-6, for contamination surveys; Health Physics Instruments, HPI 1010, tissue equivalent, multiplying ion chambers with ranges of O-l mrad/hr, X 0. 1, 1,
10, 100, 1000, and integrating ranges of 0-1 mrad, X 0.01, 0. 1
& 1, for use in emergency kits in place of the Rad Owl; 4,
IRT Corp..
PRM-110, Liquid Scintillation portal monitors, for installation in the security building and locker room.
The system operates at a 90K confidence level in the detection of 0.6 uCi Ba-133, 1.3 uCi Cs-137, 0.3 uCi Co-60 at a walking speed of 3 feet/sec (~2 mph);
MDH Industries, Model 1015 series X-ray monitor with a model 10x5-180 ion chamber, for use in place of a Victoreen condenser R-meter for reference calibrations;
"
4, basic counting systems consisting of Applied Physics Technology (APT) 15/ intrinsic Ge detectors contained in 4", cylindrical lead shields with Cd-Cu linings, Nuclear Data model 66, multichannel analyzers, Hewlett Packard model 9845B computers, Hewlett Packard
r
disk data 20 megabyte storage and Modems to other systems.
NBS traceable sources, including nobl'e gas have been used to calibrate the gamma counting systems; 2 Tennelec, Model LB5110, alpha-beta proportional, counting systems with auto sample changers; 1 Eberline, Rascal neutron survey instrument with the large sphere in addition to the PNR-4 already onsite.
No items of noncompliance were identified.
Radiation Protection - Personnel Monitorin The licensee presently uses Radiation Detection Company film badges.
The licensee's corporate organization is purchasing Panasonic TLD systems (models, UD 710A automatic reader and UD 730 tray changer and a
UD 702A manual reader).
The licensee plans to use a 4 chip badge, containing two chips each of Li2 B4 07:Cu ~nd CaS04:Tm.
The lithium borate chips contain Li B1~ and Li B
~
The TLD program will be conducted onsite by a dosimetrist employed by the licensee'
Department of Engineering Research (DER).
DER will act as a contractor during the program's first year.
The film badge program will overlap the TLD program until the TLD program has been certified by the University of Michigan.
The manual TLD system located in the radiation protection office area will be used for backup and special studies.
The licensee has been informed that the TLD system will characterize exposures due to beta, gamma, fast and slow neutrons.
The licensee has available neutron rem-meters (Eberline Rascal and-PNR-4) for use as an alternate method for evaluating neutron exposures.
No items of noncompliance were identified.
Radiation Protection - Res irator Protection IE Inspection Report No. 50-275/79-03, paragraph 10, noted that the licensee had been informed of the need to formally advise the NRC of the intent to use respiratory protective devices.
The licensee submitted a letter dated June 16.
1980, applicable to Units 1 and 2, pursuant to 10 CFR 20. 103(e), stating the intent to use respiratory protective equipment.
(HN-06-18)
No items of noncompliance were identified.
Procedures
- Waste Mana ement IE Inspection Report No. 50-275/80-04, paragraph 6, identified a number of procedures which were incomplete.
The status of these procedures was reviewed during this inspectio A-4, Chemistr Laborator Calibration Schedule, in the typing-review process, not complete; A-5, Li uid Radwaste Dischar e Mana ement, approximately 95'A complete; A-6, Gaseous Radwaste Dischar e Hang ement, approximately 85-90K complete; E-4, Outfall Sam lin ; not reviewed by PSRC; I
G-ll, Packa in, Stora e, and Inventor of Solid Radioactive Waste, major revisions required, not complete.
In addition, the licensee is revising A-2, Secondar C cle Sam lin Schedule, which had been completed and approved, as a result of the Tscensee's review of IE Bulletin 80-10, Contamination of Nonradioactive System and Resultin Potential for Unmonitored, Uncontrolled Release of Rad~oactsvst to Environment.
o action or response to the Bulletin was required; however, the licensee is including the makeup demineralizer regenerant, domestic and drinking water and firewater in the previously identified sampling schedule.
Procedure E-6, Secondar S stem Sam lin, is complete and approved.
(80-04-02)
The licensee had submitted an Offsite Dose Calculation Manual (ODCH},
Chemical Anal sis Procedure A-8, Off-Site Dose Calculations, dated A ril 15, 1980 to NRC headquarters.
The licensee stated that no response to the submission had been received from NRC.
After the inspection, the inspector learned that NRC headquarters was communicating with the licensee's corporate office staff and that an apparent breakdown in communications had occurred.
The licensee was informed by telephone.
The status of the incomplete procedures and ODCH will be examined during subsequent inspections.
(81-05-01)
No items of noncompliance were identified.
Area, Process and Effluent Monitor Calibration Previous discussions with the licensee concerning instrument calibrations have been reported in IE Inspection Reports Nos.
50-275/78-13, paragraph 8, 50-275/78-07, paragraph 7, 50-275/77-08, paragraph 5,
and 50-275/76-03, paragraph 4.c(2), 5.c, and 6.d.
The licensee's principal difficulty in confirming the vendor's (Westinghouse)
offsite calibration has involved the availability of sources traceable to the vendor's calibration.
The licensee had succeeded in obtaining single, calibrated, traceable sources, contained in specially designed caps or holders which orient the source in a reproducible
manner with respect to the detector, for the area, gas, particulate, and liquid monitors supplied by Westinghouse.
In addition, the licensee has procured four additional source holders, identical in design, to the Westinghouse holders, for each of the effluent and process monitor types and one additional holder for the area monitors.
The Westinghouse sources were certified to + 5X and specify the count rates to be produced in a calibrated properly operating systems.
The Westinghouse sources for the gas, particulate, and liquid monitors were designed to provide midrange response.
The Westinghouse area monitoring source was of relatively low intensity.
The licensee procured sources of the same nuclide but higher and lower intensities than the Westinghouse sources as well as high and low intensity sources of a different nuclide for the gas, particulate, and liquid monitors and a single higher intensity source for the area monitor.
Sources Available for Various Monitorin S stems Monitoring S stem Westinghouse Supplied.
Certified Sources Licensee Procured Sources (high and low intensit each gas particulate liquid area Sr-90 Cs-137 Cs-137 Cs-137 (low intensity)
Sr-90 8 Kr-85 Cs-137 8 BA-133 Cs-137 8 BA-133 Cs-137 (high intensity only)
The licensee has "fingerprinted" all the sources in reproducible geometries using the Ge-detector, multichannel analyzer system to permit reproducing the sources at some future time.
The Ge counting systems have been calibrated using NBS traceable sources.
The licensee plans to establish the expected monitor response, in counts per minute, for each source based on the Ge system calibration.
At the time of the inspection, the "fingerprinting" process had been completed and the calibration based on the family of sources was about to begin.,
To ease the communication problems attendant on calibration of detectors remote from the readout instrumentation, the licensee plans initially to calibrate the detectors at the location of the instrument readout.
The cabling between the detector location and readout system will be subjected to testing to confirm its proper performance.
The detector will then be calibrated at the remote location using the cable to be used during normal operation.
The tests will be documented.
Future calibrations, performed after operations commence, will be performed with the detector at the readout location to minimize workman exposure (ALARA) and the cable will be tested to confirm continued proper operatio The monitoring systems provided by SAI/RadeCo will be calibrated onsite by the manufacturer's personnel, and solid sources to be used in future calibrations will be characterized as a part of that calibration process.
The licensee's continuing activities with respect to calibration of these systems will be examined during a subsequent inspection.
(81-05-02).
No items of noncompliance were identified.
Preo erational Testin The status of outstanding preoperational tests selected for review (previously identified in IE Inspection Report No. 50-275/80-04, paragraph 5) was examined.
In those cases where preoperational tests had been completed, approved and accepted by operations, test results were examined to assure that the test results were within the previously established acceptance criteria.and, where applicable, deviations from acceptance criteria were properly identified and disposed in accordance with the licensee's administrative procedures.
Only one test, identified in IE Inspection Report No. 50-275/80-04 as incomplete, has been completed since that inspection.
The following test is complete and has been accepted by operations:
23.1 Main Control Room Heatin, Ventilatin, and Air Conditionin S stem Addendum 1 - Test of 0 erabilit of Time Totalizer added to Control Room Ventilation S stem Filter Unit 39 Totalizer operation was tested in both modes incorporating the use of filter unit 39.
New section added to above test:
Addendum 3 - not written, purpose of test is to evaluate the effect of the emergency diesel exhaust on control room air quality when the control room air pressurization system is in use.
No items of noncompliance were identified.
IE Bulletin Circular Followu The licensee has established a formal system for documenting receipt, distribution, action, and response to the identified documents..
Onsite a specific individual has been assigned responsibility and
'
-10-maintains manual records.
The licensee reported that a similar but computer based system is used in the corporate office.
IE Bulletin No. 80-03, Loss of Charcoal from Standard T
e II, 2 inch, Tra Absorber Cells The licensee performed the visual inspection in a timely fashion and reported the results to the corporate office.
The response to NRC, required within 45 days of the date of the Bulletin, February 6,
1980, was actually dated September 24, 1980.
Mr. J. Shiffer, Manager, Nuclear Plant Operations stated that the delay had probably been occasioned by the establishment of the Department of Nuclear Plant Operations and the concurrent organizational changes.
The system presently in place in the corporate office for handling bulletins and circulars should preclude similar occurrences in the future.
This matter is considered closed.
(IB-80-03)
IE Circular Nos.
79-15 and 79-21, applicable to both Units were discussed but reported only with respect to Unit 1 in IE Inspection Report No. 50-275/80-04, paragraph 7.
These matters are considered closed with respect to Unit 2.
(IC-79-15 and IC-79-21).
IE Circular No. 80-14; Radioactive Contamination of Plant Demineralized Water S stem and Resultant Internal Contamination of Personnel No written response was required.
The licensee documented an internal response on September 29, 1980.
The circular was reviewed for applicability and appropriate corrective actions were initiated.
This matter is considered closed.
(IC-80-.14)
IE Circular No. 80-18:
CFR 50.59 Safet Evaluations for Chan es to Radioactive Waste Treatment S stems No written response was required.
The licensee reviewed the Circular and initiated draft changes to Administrative Procedure No.
C-1 h
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d which provides for safety evaluations of changes in design, it appeared that safety evaluations might be =limited to "safety related equipment" rather than the facility and/or operations as described in the FSAR.
The licensee committed to modify the procedure to assure that required safety evaluations would be performed.
This matter is considered closed.
(IC-80-18)
No items of noncompliance were identified.
Plant Tour Portions of the facility were toured with special emphasis on the following areas:
-11-Counting laboratories, observed th'e recently installed Ge-multichannel analyzer equipment and observed operation; control room, facilities for calibration of process and effluent monitors; interim and permanent post accident sampling systems; radwaste solidification area; control room air pressurization system, and one steam generator hydrolance and channel head access areas.
With respect to the steam generator it was noted that access to certain areas was difficult and had been further complicated by some of the seismic supports which have been added.
The advantages of planning for future outages by the design and fabrication of tents and other protective and contamination control systems or possible modifications to improve access prior to operation were discussed.
No items of noncompliance were identified.
12.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on March 13, 1981.
The inspector summarized the inspection scope and findings.
The inspector reviewed the discussion relating to "safety evaluations" required by 10 CFR 50. 59 and confirmed the licensee's commitment as stated in paragraph 1 '0