IR 05000275/1990028
| ML16341F931 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon |
| Issue date: | 12/27/1990 |
| From: | Cillis M, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML16341F930 | List: |
| References | |
| 50-275-90-28, 50-323-90-28, NUDOCS 9101140113 | |
| Download: ML16341F931 (14) | |
Text
U.
S.
NUCLEAR REGULATORY COMMISSION
REGION V
Report Nos.
50-275/90-28 and 50-323/90-28 License Nos.
Pacific Gas 8 Electric Company 77 Beale Street, Room 1451 San Francisco, California - 94106 Facility Name:
Diablo Canyon Units 1 and
Inspection conducted:
November 26, 1990, through December 5, 1990 Inspection by:
G.
en)or a
>a ion pec>a
>s Approved by:
G P.
u as,
>e Reacto adiological Protection Branch
a e
>gne a
e igne
~Summer:
A~It A.
Routine unannounced inspection by one regionally based inspector of radioactive waste systems, including followup items and tours of the licensee's facilities. Inspection modules 84750, 83750 and 92701 were addressed.
Results:
In the areas inspected, the licensee's programs appeared adequate to accomplish their safety objectives.
No violation or deviations were identified.
Inspection at:
Diablo Canyon Site, San luis Obispo County, California 9102240223 902227 F'DR ADQCK 050002" ~
G PDR
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1.
Persons Contacted A.
Licehsee DETAILS
.~W.
G. Crockett, Assistant Plant Manager, Support Services
~D.
B.
Miklush Assistant Plant Manager, Operations Services
~J.
V. Boots, chemistry Manager
"R. Gray, Radiation Protection Manager
- R. Washington, I8C/ILC Manager
~W.
D. Barkhuff, QC Manager
~M. 0. Sommerville, Radiation Protection, Senior Engineer
- J.
E. Gardner, Senior Chemical Engineer T.
L. Grebel, Supervisor, Regulatory Compliance C.
C. Miller, Radiation protection Engineer E.
S.
Wessel, Chemical Engineer D.
Chen, Chemical Engineer R.
Lund, Radiation Protection, General Foreman T.
L. Irwing, Radwaste Foreman J.
R. Tinlin, IEC Foreman P.
W. Baxter, Training Instructor R.
C.
Randal, Power Production Engineer, Operations A.
O. Taylor, Chemical Engineer D.
R. Stermer, System Engineer Denotes those individuals present at the exit interview conducted on December 5, 1990.
Additional discussions were held with other members of the licensee's staff.
2.
Radioactive Waste S stems Water Chemistr and Radiolo ical nvsronmen a
on> orsn
Audits and A
raisals The inspector reviewed the following licensee audit reports:
o Audit Report ¹89815T, "Radioactive Material Management,"
dated October 13, 1989.
o Audit Report ¹90804T, "Offsite Dose Calculation Procedure (ODCP) and Radioactive Effluent Monitoring," dated October 30, 1990.
o Audit Report ¹90821T, "In-Plant Radiologic'al Control," dated October 31,1990.
The audits appeared to cover a wide cross section of the areas that were examined.
Audit findings were addressed in a timely manner.
The audit reports did not identify any regulatory violation Procedures Procedures applicable to the subject areas that were examined during this inspection were reviewed and were found to be satisfactory.
The following list provides an example of some the procedures that were reviewed; AP C-253,
Rev 15 AP C-,253S1,
"Dewatering Control Program",
Rev
RCP D-635, "Shipping of High Activity Radioactive Materials Using PG8E Post Accident Sampling Shipping Pkg.",
Rev
STP G-14, "Operability Determination of Post Accident Sampling Program",
Rev 8 CAP A-ll, Liquid Radwaste Processing System Selection",
Rev
EP RB-15, "Post Accident Sampling System",
Rev 4 STP I-100A, "Containment Air Radiogas Monitor (RM-12) and Containment Air Particulate Monitor (RM-11) Functional Test" STP I-103A, "Functional Test of Gas Decay Tank Gas Discharge Monitor RM-22 Data Sheet" Chanches No major changes had occurred'.since this functional area was previously rev iewed.
Pro ram Im lementation A.
Post Accident Sam lin S stem (PASS The licensee's proqram for assuring compliance with TS 6.8.4.e,
"Post Accident Training" was examined.
The examinat'ion inclu'ded a review of applicable procedures and training records, discussions with the lead chemical engineer and training instructor responsible for implementation of the PASS program, and by direct observations of the licensee's PASS in Unit l.
The review of records disclosed that the licensee has established procedures for conducting PASS training, analysis of samples, and performing maintenance of sampling and analysis equipment.
The.
inspector also noted that the licensee PASS sample analysis results for surveillance testing conducted over the past year were well within the "acceptance criteria" that have been established in surveillance test procedures.
The PASS analysis results compared rather well with the licensee's normal sampling system.
The
examination disclosed that the licensee utilizes the PASS frequently and that all qualified users operate the system frequently.
The inspector concluded that the licensee's PASS program met or exceeded TS 6.8.4.e requirements.
Plant S stems:
Air Cleanin S stem The inspector verifi ed that the surveillance requir ements for the control room ventilation system, auxiliary building safeguards air filtration system and fuel handling building ventilation system were performed at the frequencies specified, in TS 3/4.7.5, 3/4.7.6 and 3/4.9.12.
Applicable procedures associated with performing the TS survei llances to verify system operability and testing; such as, flow, carbon analysis, pressure drop checks and DOP testing of HEPA filters, for the period of 1989 through November 1990, were reviewed.
The inspector concluded that the licensee's surveillance programs for these systems exceeded TS requirements.
Radiation Honitorin S stems The inspector verified that the surveillance requirements for radiation monitoring instrumentation were performed at the frequencies specified in TS 3/4.3,3.
Applicable surveillance test procedures for performing the channel checks, source checks, channel calibration and channel functional test, for the period of 1989 to date were reviewed.
The inspector also verified that the alarm/trip set points were consistent with the values listed in the TS and applicable licensee procedures.
The inspector concluded that the licensee was maintaining the radiation monitoring instrumentation that are required for plant operations in accordance with the TS.
Solid Waste Pro ram Selected records associated with the licensee's processing and storage of solid radioactive wastes were examined.
No significant changes had occurred since this area was last examined.
The examination disclosed that the licensee has an aggressive waste minimization program in place.
Responsible plant staff personnel continue to explore methods for minimizing the generation of wastes. ~
'he inspector concluded that the licensee's solid waste program were consistent with TS 3/4. 11.3 and the licensee's Commission approved process, control program.
Process Control Pro ram (PCP)
The inspector reviewed applicable procedures and records associated with the licensee's approved PCP.
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No significant changes have occurred since the PCP was previously reviewed.
The PCP was found to be consistent with licensee procedure AP C-253,
"Process Control Program" which had been
,submitted to the NRC in the licensee's Semiannual Radioactive
~
Effluent Release Report of 1989.
The inspector concluded that the licensee's PCP program was consistent with TS 6: 13, "Process Control Program."
F.
Radioactive Effluent The inspector reviewed records-of reactor coolant system chemistry for 1989 and 1990.
The licensee had performed analyses of dissolved oxygen, fluoride, chloride, and dose equivalent Iodine-131 at the frequencies required by TS 3/4.4.7,
"Chemistry" and TS 3/4.4,8, "Specific Activity."
Sample results were within TS required concentrations.
G.
H.
The inspector also reviewed the semiannual radioactive effluent release report.
The report summarizes the gaseous and liquid effluent releases made from Diablo Canyon Power Plant, Un)t 1 and Unit 2, for the first and second quarter of 1990.
The report contained the information specified in TS 6.9. 1,6 and was presented in the format of Regulatory Guide 1.21, Appendix B.
No anomalous measurements, omissions, or abnormal trends were observed.
Radiolo ical Environmental Monitorin
This item is addressed in Section 2 'of Region V Inspection Report 50-275/90-20.
Offsite Dose Calculation Procedure (ODCP)
The licensee made the following changes to the ODCP since the previous inspection:
(1).
Completed the perennial update to the "5 years-running historical average" meteorological dispersion factors X/g and D/g because values for 1984 were dropped and values for 1989 were added.
(2).
Changed the parameters in the Percent Release Rate Limits-PRRL (Appendix 2) expressions because of dependency on new "5 year history average 'eteorological parameters X/g and D/g.
The changes were approved by the Plant Staff"Rev'iew Committee on April 5, 1990, and was submitted to the NRC in the licensee's Semiannual'adioactive Effluent Release Report for the period ending on June 30, 1990.
The licensee was maintaining its previous level of performance in this program area.
Observed aspects of the program were adequate in meeting the licensee's safety objectives.
No violations or deviations were identifie I'
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Followu (MC 92701)'he following provides a status of followup items that were reviewed during the inspection period:
0 en Items 50-275/IN-90-31 50-275/IN-90-33 50-275/IN-90-35-90-08 an ose
e inspec or veri ie a
e icensee a
receive e
is e
Information Notices (INs) and had either completed an evaluation or were in the process of performing an evaluation of the INs in accordance with established procedures.
This matter is closed.
0 en Item 50-275/90-20-01 (Closed):
Inspection report 50-275/90-20 i en i ie a
e ca i ra sons of two continuous air monitors referenced in the FSAR had not been calibrated at the frequencies specified in licensee procedures.
A review of the licensee s evaluation regarding this item was conducted.
The licensee's evaluation revealed that the minimum number of monitors identified in the FSAR were still operable and were in current calibration and that the monitors that were past due for calibration had no impact on plant operations.
The inspector noted that the monitors that were in question had since been calibrated.
Maintenance procedure 18C MP 1.3-4 was revised to include the FSAR commitments and the monitorinq equipment was included on the Recurring Task Schedule, with proper priority for performing the calibrations.
This matter is closed.
0 en Item 50-275/90-09-01 (Clgsed):
This item involved some radioactive ma eria a
was oun in an Sea-Train which was not posted as a
radioactive material storage area.
The material had been placed in the Sea-Train without the approval and/or knowledge of the radiation protection group.
The licensee's evaluation of this item was reviewed and found to be satisfactory.
The evaluation described in Action Request
, 8 A0184275, includes provision performing tailboard training of 18C and returning contractor personnel on the guidelines provided in licensee procedure AP D-55.
This matter is closed..
0 en Item 50-275/90-09-02 (Closed):
This item was related to poor ouse eepinq pro ems a
were o served in radiological controlled areas during previous inspections.
A review of licensee Action Request,
A0188154, and a licensee memorandum, dated August 16, 1990, addresses the concern satisfactorily.
In addition the inspector noted a significant improvement in housekeeping during this inspection 'period (see Section 4,
,
below).
This matter is closed.
Facilit Tours (MC 83750)
Tours of the licensee's facilities were conducted during the inspection period.
Radioactive waste storage areas and the radioactive material receipt areas at the warehouse were included in the tours.
Independent radiation measurements were made using an ion chamber survey instrument,
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h1odel R0-2, serial number 2691, due for calibration on January 5, 1991.
The following observations were made:
(a)
Posting and labeling practices were consistent with 10 CFR Parts 19.11 and 20.203.
(b)
Several non work related magazines were observed within the radiological controlled areas.
(c)
Considerable improvements in lighting and'plant cleanliness were noted since the previous inspection.
(d)
All portable instruments observed were in current calibration.
(e)
All personnel observed in the licensee's controlled areas were equipped with appropriate dosimetry devices.
(f)
Several polyethylene floor drain lines were crimped.
The inspector reported the above observations to the licensee's staff after each tour.
Immediate actions were taken by the licensee's staff to correct the inspectors findings.
The licensee s program in this subject area appeared capable of meet>ng its safety objectives.
No violations or deviations were identified.
5.
Exit Interview (HC 84750)
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The inspector met with the individuals denoted in paragraph 1 at the conclusion of the inspection on November 1, 1990.
The scope and findings of the inspection were summarized.
The licensee.was informed that no violations or deviations were identifie It
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