IR 05000369/1981001
| ML19345G354 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 02/09/1981 |
| From: | Gibson A, Montgomery D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19345G348 | List: |
| References | |
| 50-369-81-01, 50-369-81-1, NUDOCS 8103180491 | |
| Download: ML19345G354 (5) | |
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t UNITED STATES o
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NUCa. EAR REGULATORY COMMISSION
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REGION 11
'01 MAqlETTA ST., N.W., SUITE 3100 v,
e, ATLANTA, GEORGIA 30303
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Report No. 50-369/81-01 Licensee: Duke Power Company Docket No. 50-369 Facility Name:
McGuire Unit 1 License No. CPPR-83
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Inspection at McGuire Site O " b d/
Inspector:
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D. M.
ongtpomer 'G
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Date Signed C
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I - "'_O f Acproved by:
A. F. Gibson, Section Chief, FFMS Branch Date S1gned
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Dates of Inspection: January 5-7, 1981 SUMMA'4Y Areas Inspected This routine,- unanr.ounced. inspection involved 15 inspector-hours orsite in the areas of quality control and capability tests for tf:- measurement of radioactivity in liquid and gaseous effluents.
Results Of the two areas inspected, 'no items of excompliance or deviations were identified in two areas.
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I DETAILS I
1.
Persons Contacted Licensee Employees-
- V. M. Sample, Projects License Engineer
- D. B. Lampke, Engineer
- W. F. Byrum, Counting Room Supervisor
- T. J. Keane, Station Health Physicist
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M. J. Birch, Corporate Health Physics
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A. W. Roy, Quality Assurance Supervisor NRC Resident Inspector T. J. Donat
- Attended exit interview.
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Exit Interview
.The inspection scope and findings were summarized on January 7,1981 with those persons indicated in paragraph 1 above.
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Procedure Review a.
Tha inspector reviewed tt following procedures and discussed the-review with licensee repre entatives as detailed in paragraphs 3.b -
3.e.
.(1) PT/0/B/4600/23, Count Room Quality Assurance Gamma Well, Rev. O, 10-9-80.
(2) PT/0/B/4600/27, Count Room Quality Assurance Beta Gamma Instru-mentation,-Rev. O, 10-3-80.
(3) PT/0/B/4600/29, Count -Room Quality Assurance Prias Liquid Scin-tillation Counter, Rev. O, 10-16-80.
(4) PT/0/B/4600/33,- Count. Room Quality Assurance Alpha Instrumenta-tion, Rev. - 0,-10-9-80.
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(5) CP/0/A/8200/07, E-Bar Determination,12-l'l-80
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(6) CP/0/A/8600/01, Sampling'the Radwaste and Boron Recycle Systems,
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10-20-80.
b.
. The inspector - noted that procedures for E-bar determination and sampling of liquid wastes had-been approved.
A-licensee representa-
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tive stated that.a gross alpha analysis procedure would not be written
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since these analyses would be performed under contract. This closes out a previously identified item (369/80-17-01).
c.
The inspector noted that procedures were written to provide acceptance criteria and corrective action associated with instrument QC checks.
These procedures also corrected the deficiencies previously identified in procedures, HP/0/B/1001/05, HP/0/B/1001/03, and HP/0/8/1001/08.
This closes out previously identified items (369/80-17-03 and 369/80-17-04).
d.
The inspector noted that some counting room and sampling procedures have not been completed and approved. Tnese include the following:
(1) HP/0/B/1001/08, Quality Assurance and Sample Traceability.
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(2) HP/0/8/1003/07, Preparation of Count Room Sources (3) _PT/0/B/4600/30, Count Room Quality Assurance Aston Liquid Scin-tillation Counter (4) PT/0/B/4600/31, Count Room Quality Assurance for GeLi Detectors
.(5) PT/0/B/4600/32, Count Room Quality Assurance for NaI Detectors (6) HP/0/B/1003/11, Composite Samples Final approval of _ these procedures will be considerec an open item (369/80-01-01).
e.
The inspector discussed procedure approval for radiochemical analyses to be performed by a licensee contractJr. This had previously been identified as an open item (369/80-17-21).
The inspector met with representatives from Duke Power Corporate Health Physics, Quality Assurance Department, and McGuire Nuclear Plant regarding the requirement-for procedure review and approval.
The inspector stated that proposed Technical Specifications require written procedures for all applicable procedures in Appendix
"A" of Regulatory Guide 1.33, Revision 2, February 1978.
In addition, each procedure must be reviewed and approved by the Station Manager or his designate.
Regulatory Guide 1.33 specifies procedures for the control of radio-activity including sampling and monitoring. Duke Dower representatives stated that the audit and approval of the contractor performing radio-chemical analyses by the Quality Assuranc ? 'epartment ensures the quality of the analyses and that review and approval of centractor's procedures was not required by the Technical Specifications.
The inspector stated that Quality Assurance audits of the contractor program did not relieve the plant of the requirement to review and approve procedures used by contractors to perform analyses or surveillance activities that are required by Technical Specifications.
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The inspector stated that this area would continue to be carried as an open item and that unless the. Technical Specifications were modified prior to licensing, failure to review and approve contactor procedures used for analyses of liquid effluents would constitue noncompliance when the plant is-licensed and operating.
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4.
Capability Test for Analysis of Liquid Effluents
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The: inspector reviewed the results of radiochemical analyses of simulated samples submitted to the-licensee by NRC. The simulated samples included:
liquid waste, charcoal. cartridge, and particulate filter. The samples were
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analyzed. for gamma-ray emitters by. gamma-ray spectrometry.
The liquid sample was also analyzed for tritium and radiostrontium by the licensee contractor.
The acceptance criteria are given in Attachment I and the analytical results and comparison in Table 1.
The results show agreement
for all. samples and radionuclides except Cs-137 where there was possible agreement. The licensee values for the particulate filter appeared to be
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systematically higher than NRC values. This is probably due to differences in geometty between the spiked filter and the calibration gecmetry.
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TABLE 1
Results of Capability Tests of McGuire, August 1980 CONCENTRATION. MICROCURIES/CC Ratio lan g BpJgen.
ficGu i re H!!C McGuire/NRC Rosclitgjoa Compa rison Simulated H-3 7.6010.01E-3
~6.2910.06E-3 '
1.22
Agreement 1.20 105 Ag reemen t Liquid SR-89 3.810.2E-3 3.110.1E-3
. Waste
- S r-90 '
5.910.1E-4 6.210.2E-4
.95'
Agreement Co-57 2.310.2E-4 1.5710.05E-4 1.27
Ag reement Co-60 1.3210.05E-3 1.1210.03E-3 1.17
Agreement Cs-134 9. 410. 4 E-4 8.610.2E-4 1,09
Ag reement Simulated Ba-133 5.2510.1E-2 5.010.1E-2 1.05
Agreement Cha rcoa l Ca rt ridge Simulated
.Co-57 6.710.8E-4 6.310.2E-4 1.06
Agreement Particu-
'Co-60 2.810.05E-3 2.1310.06E-3 1.31
Ag reemen t late Cs-134 1.6310.040-3 1.4010.05E-3 1.16
Ag ree.run t Filter Cs-137
- 5.6110.05E-3 4.110.1E-3 1.36
Possible
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Ag reemen t s
1