IR 05000321/1980012
| ML19323J103 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/22/1980 |
| From: | Cunningham A, Jenkins G, Macarthur T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19323J096 | List: |
| References | |
| 50-321-80-12, 50-366-80-12, NUDOCS 8006170775 | |
| Download: ML19323J103 (9) | |
Text
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UNITED STATES f
'4'n NUCLEAR REGULATORY COMMISSION
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REGION 11
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101 MARIETTA ST., N.W.. SUITE 3100 o
ATLANTA, GEORGIA 30303 s
APR 2 21980 Report Nos. 50-321/80-12 and 50-366/80-12 Licensee: Georgia Power Company
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270 Peachtree Street Atlanta, Georgia 30303 Facility Name: Edwin I. Hatch Docket Nos. 50-321 and 50-366 License Nos. DPR-57 and NPF-5 Inspection at Edwi I a h, Eaxley, GA., Environmental Center, Decatur, GA E.c
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Inspe ors:
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Cunn am Date Signed he
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T.~C. Mac hsr Dte Signed a
Approved by:
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G. R. J ns, Section Chief, FFMS Branch Da'te Signed
SUMMARY Inspection on March 10-19, 1980
Areas Inspected This routine, unannounced inspection involved 66 inspector-hours on site in the areas of radiological and nonradiological environmental protection including management controls, review of previous enforcement matters, review of environ-mental surveillance, review of special surveillance and study activities, status
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review of licensee event reports, selected soil and groundwater independent
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sampling.
Results c
Of the six areas inspected, no items of noncompliance or deviations were identi-fied in five areas; one item of noncompliance was found in one area (deficiency:
environmental monitoring (50-321/80-12-01, 50-366/80-12-01) paragraph 6).
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O DETAILS 1.
Persons Contacted
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l Licensee Employees
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- C. R. Miles, Jr., Quality Assurance Field Supervisor
- M. Manry, Plant Manager
- W. H. Rogers, Health Physics Supervisor
- D. Smith, Laboratory Supervisor
- T. Greene, Assistant Plant Manager
- G. E. Spell, Jr., Senior Quttity Assurance Field Representative
- B. L. Maulsby, Supervisor, Environmental Affairs Center
- G. A. Breece, Environmental Specialist
- C. B. Boatwright, Senior Quality Assurance Engineer
- W. R. Woodhall, Jr., Power Supply Laboratories Manager NRC Resident Inspector
- R. Rogers
- Attended exit Interview at Hatch plant site (March 14, 1980).
- Attended exit interview at Environmental Affairs Center (March 19, 1980).
2.
Exit Interview The inspection scope and findings were summarized on March 14, 1980, at the Hatch Plant site, and on March 19, 1980, at the Georgia Power Company Environmental Center with those persons indicated in paragraph 1 above.
The item of noncompliance involving environmental monitoring as cited herein, was discussed. No further response by the licensee was required.
Additional corrective action concerning licensee event report 50-321/79-012, addressing an unmonitored releare path for low level radioactive fluids (IE Report Nos. 50-321/79-12 and 50-366/79-16), was also discussed on both dates indicated above. On March 19, 1980, during a meeting at the NRC Region II Office, a Georgia Power Company management representative stated, in response to discussion of the subject corrective action, that estimated completion of the permanent fix involving enclosure of condensate transfer pumps for Units I and 2 condensate storage tanks was six weeks.
3.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance (50-321/78-40-01, 50-366/78-49-01) Failure to provide procedures assuring the quality of Environmental Technical Specifications program results including analytical measurements. The inspector reviewed the licensee's corrective actions in response to this item. Quality Assurance procedures HNP-7650 and HNP-7651 were prepared, approved, and implemented'
as. required. The procedures addressed Technical Specifications implementa-tion and analytical quality control, respectively.
There were no further i
questions regarding this item.
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(Closed) Noncomplaince (50-321/40-78-02, 50-366/78-49-02) Failure to conduct semi-annual aerial survey of HNP-Bonaire Transmission Line during the 1978 calendar year.
Inspection disclosed that required surveys were resumed during 1979. There were no further questions regarding this item.
4.
Unresolved Items
. Unresolved items were not identified during this inspection.
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5.
Management Controls Section 5.0 of Appendix B to Facility License NPF-5 defines the manage-
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a.
ment and administrative controls established to implement the Environ-mental Technical. Specifications. Requirements cited therein include y
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assignments of responsibility, review and audit functions, routine and
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nonroutine reporting criteria.
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b.
The-inspector conducted a detailed review of licensee audits of environ-
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mental montioring and surveillance requirements. During the period j
June 8, 1979, through January 9, 1980, the licensee conducted twelve audits which included the annual audit of Appendix B Technical Speci-
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fications implementation (Audit No. QA-79-ETS-1). The remaining
internal audits addressed specific environmental procedures and programs; e.g., the annual drinking water survey defined in Appendix B Technical
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i Specification Section 3.2.
During the above period, the licensee also i
audited three of its environmental contractor programs and facilities.
Inspection of licensee audits included the following:
(1) a detailed
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review of each audit report; (2) discussion of respective audit findings, (3) review and discussion of responses and corrective actions associated
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with such findings.
Inspection disclosed that all environmental audits and related follow-up activities reviewed were consistent with Technical Specification requirements and licensee quality assurance i
procedures. There were no questions regarding this item.
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Section 5.6 of Appendix B Technical Specifications lists procedural c.
requirements for all activities involved in implementing the environ-mental conditions and comritments defined therein. Inspection included the following:
(1) review of procedures; (2) review and discussion of
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revisions to such 7cedures and the Environmental Programs Description
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. Document (EPDD) implemented during the period December 9, 1978 through March 19,.1980; (3) review of licensee compliance with procedures; (4)
review of procedures established to ensure quality assurance of environ-
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mental program results, including analytical measurements (50-321/
78-40-01 and 50-366/78-49-01), viz, licensee procedures RRP-7650 and HNP-7651.
Inspection disclosed that all procedures reviewed were consistent with Technical Specification requirements. There were no
further questions regarding this item.
d.
Section 5.7 of Appendix B Technical Specifications defines routine and
nonroutine plant reporting requirements. At the time of inspection,
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'the Annual Environmental Surveillance Report for the period ending December 31,.1979, was not yet submitted to the NRC. The subject report is required to be submitted within 90 days after January 1 of each year..This report will be reviewed during a subsequent inspection.
The inspector, however, reviewed nonroutine environmental reports submitted to the NRC during the period December 9, 1978 through March 19, 1980. Licensee Event Report No. 50-321/1979-021 addressing an unmoni-tored release path for low level radioactive fluids was reported to NRC Region II on March 22, 1979 (IE Report Nos. 50-321/79-12 and 50-366/79-16). The status of this event is discussed in paragraph 8.
6.
Environmental Monitoring
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Aquatic abiotic monitoring parameters defined in Appendix B Technical a.
Specifications Section 3.1.1 include plant cooling water intake and discharge temperture and pH, and plant cooling water discharge free chlorine concentration. Inspection included review and audit of the subject monitoring data and reports for the period December 9, 1978, through March 14, 1980.
Inspection disclosed that all parameters were monitored as required and that limits assigned to each parameter were
not exceeded. There were no questions regarding this item, b.
' Aquatic biotic monitoring parameters defined in Appendix B Technical Specifications Section 3.1.2 include benthic macroinvertebrates, ichthyoplankton entrainment, and impingement of organisms.
Inspection consisted of review and audit of the subject monitoring data and reports for the period January 2,1979, through March 19, 1980.
Inspection disclosed that monitoring prog ams of entrainment and impingement were commenced on February 1,1979, contrary to the com-mitted date of January 2, 1979, required by Appendix B Technical
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Specifications Sections 3.1.2.1.2 and 3.1.2.1.3, respectively. The inspector discussed the above findings with licensee representative, and informed them that, not withstanding compliance with the monitoring requirements subsequent to February 1, 1979, failure to initiate the subject monitoring programs, as specified, constituted an item of noncompliance (50-321/80-12-01, 50-366/80-12-01). A licensee repre-sentative stated that although some preliminary cursory entrainment
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and impingement monitoring was conducted prior to February 1,1979, such monitoring was not formally commenced until February 1, 1979.
The' licensee representative further stated that the error in commence-ment of the subject monitoring programs was later noticed. Based upon discussions with licensee representatives, the inspector informed them i
that no additional response to the cited noncompliance item was required.
Inspection of benthic monitoring data, records and reports disclosed that monitoring was implemented as required. There were no further questions.
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7.
Special Surveillance And Study Activities Section 4.1 of Appendix B Technical Specifications requires semiannual aerial surveys of the HNP-Bonaire transmission line right-of-way
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until stabilization of soil and vegetation along that line has been achieved.
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Inspection of survey reports and pertinent licensee correspondence files
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disclosed that aerial surveys were conducted on April 30, 1979 and October 30,
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1979. These surveys indicated that scattered areas of soil erosion had i
been mitigated and the right-of-way appeared to be stabilized. The licensee plans to discontinue the subject surveillance as provided for in the speci-
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fication.
8.
Status Review of LER-50-321/1979-021
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Licensee Event Report (LER) 50-321/1979-021 was originally submitted
- to NRC Region II on March 28, 1979. Supplement I to Revision 5 of the
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LER (dated March 3, 1980) discussed the following:
(1) the initial
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observation by two chemical radiation technicians who reported water bubbling out of the ground near piezometer P17B; (2) actions taken by the licensee, a private contractor, and the NRC with respect to the
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initial occurrance, subsequent events and investigations relating to a number of additional releases of tritiated water to the water table
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and aquifer at certain areas of the plant site.
i b.
As noted in Section 2.4.1 of Supplement I to the 1978 HNP Annual l
Report (dated June 1979), higher than background readings for tritium have been documented in the north subsurface drainage ditch and at
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piezometer N7A approximately 10 feet south of condensate storage
tank 1 i'nce the fourth quarter of 1977. The average of the readings
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through 978 at location N7A was approximately 1.5E3 pCi/2 of tritium.
1977 readings at the North ditch were as follows:
1.40E2 (May 16, l
1977), 2.20E2 (August 14, 1977), 9.50E2 (November 16, 1977) pCi/t tritium. During this same time, the control sample from Deen's Landing l
showed no activity above the minimum detectable level of IE2 pCi/E.
- The report states that although these readings were noted to be high there was no cause for alarm since the levels were still quite innocuous.
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In mid June of 1978, camples from P17B and P16 (next to N7A) showed 8.5E2 pCi/A and 1.4E5 pCi/A, respectively. Samples taken in August 1978, at these two locations, showed increased activity levels of 1.1E4
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pCi/A at Pl?B and 1.5E5 pCi/t at P16. Activity levels in the North
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ditch rose steadily during the 1978 quarterly sampling periods from
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2.5E2 pCi/1 to 2.4E3 pCi/A in the third quarter and dropped to 1.3E3 pCi/2 in the fourth quarter.
Concurrently, during the latter half of
1978, the tritium activity at P17B rose sharply from 8.5E2 pCi/A in June to 2.5E5 pCi/f in December.
It appears that up to this time, no serious investigation of the cause of the elevated readings had been
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started. On March 20, 1979, water was observed bubbling out of the ground near P17B. Analysis of this water showed tritium activity of 1.1E6 pCi/A. On April 30, 1979, an NRC inspector was dispatched to the' site to collect five offsite samples. These samples, analyzed by Radiological Environmental Scientific Laboratory, yielded the results shown in Table 1.
In May 1979, an NRC inspector collected eight onsite samples (Report c.
Nos. 50-321/79-12 and 50-366/79-16). Sample locations and respective
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-5-findings are summarized in Table II. At this time a lictasee repre-sentative stated that a design change to relocate the pumps within the retaining wall had been submitted. This condensate storage transfer
item (321/79-12-05,50-366/79-16-05) remains open, pending completion of construction.
d.
In July 1979.an NRC inspection team sampled 10 onsite locations.
- Sample data-are listed in Table III. During this same time, samples obtained and analyzed by the licensee indicated that the area around P-16wasdecreasinginactivityslightly,butshowedlevelsinthe neighborhood of 10 pCi/1. Samples taken from N9B showed a sharp increase from 10 pCi/1 to 104
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pCi/A. The North ditch area indicated levels of 103 pCi/A.
During the subject inspection (March, 1980), the inspectors obtained e.
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35 water and 8 soil samples.
The samples were split with the licensee and the remaining aliquots were returned to the NRC Regional Laboratory for analysis of tritium content, in the case of all water samples, and
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a standard gamma spectrum of all soil samples and ten selected water j
samples. Table IV lists all samples and their respective on-site locations. Analytical results for both NRC and licensee samples will j
be presented and discussed in a subsequent inspection report.
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Two sources of tritium leakage have thus far been identified. The first source was identified as a temporary line carrying nitrogen to the feedwater heaters from a tank in the yard which was located adjacent to piezometer number 17B. The open end of this line was capped off and a coupling in the turbine building was removed ar.d the line capped so as to remove this
~ The second source was discovered to be leakage from the condensate source.
storage tank transfer pumps. Presently, cons ~truction in progress will house the pumps within the CST retaining walls and prevent any further leakage.
Although there has been a small release of tritium offsite as shown by an increase of tritium concentration at the east subsurface drainage system from 168 pCi/1 to 5740 pCi/A, the release is small and results in insignifi-cant doses to the public. The maximum permissible concentration (10CFR20)
for tritium in water in unrestricted areas is 3X108 pCi/1.
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Rivcr end Groundwater Samples-Taken by NRC l,.
(April 30, 1979)
Activit;'
Sample Location (pCi/1)
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1.
Altamaha-US1 North 612 E2 2.
Altamaha US1 South 6 i 2 E2 3.
Boy Scout Camp Altamaha River 4 1 2 E2 4.
Dea'd River Area Downstream of site 4 1 2 E2 5. -Discharge Structure Onsite 10 i 2 E2
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TABLE II Subsurface Drainage and Groundwater Samples Taken by NRC (May 7-11, 1979)
Activity Sample Location (pCi/1)
1., Outfall #1 Subsurface Drainage (N)
<2E2 2.
Outfall #2 Subsurface Drainage (E)
4E2 3.
Well #1 E. of Cooling Towers
<2E2 4.
MH #18 E. Outfall 4E2 5.
T-15 CST-1 (NE)*
OE2 6.
P-17B Diesel Building (E)
5E5 7.
P-16 CST-1 (N)
9E5
T-6 Diesel Building (E)
<2E2
- CST: Condensate Storage Tank
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TABLE III
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River Subsurface and Croundwater Samples Taken by NRC (July 1979)
i Activity Sample Location (pCi/1)
1.
MH #18
. East Outfall
<1.5 E2 2.
P-17B '-
Diesel Building (E)
3.9 E4 3.
SS #2 Subsurface Drainage (E)
<1.5 E2
- 4. 'Wel'1 #1 E. of Cooling Towers
<1.5 E2 5.
T-15 CST-1 (NE)*
4.7 E2
'6.
T-6 Diesel Building (E)
<1.5 E2 7.
Upstream River Upstream of Plant Site
<1.5 E2 8.
Downstream River Downstream of Plant Site
<1.5 E2 9.
SS #1 Subsurface Drainage (N)
8.8 E2 10.
P-16 CST-1 (S)
6.0 E4
- CST: Condensate Storage Tank
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TABLE IV
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NRC/ Georgia Power Company Samples taken March 31 - April
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sH Activity Sg' le Location h
Analysis (pCi/1)
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1.
Deens Landing Upstream of Plant HO H
Gamma
Site
,
2.
Intake Structure At Plant site HO H
Gamma
8 3.
Dead R,iver Downstream of HO H
Plant Site
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4.
T-16 CST-1 (N)*
HO H
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5.
T-19 CST-1 (SE)
H0 H
3 6.
T-15 CST-1 (NE)
H0 H
,
s 7.
T-20 CST-1 (SE)
HO H
8 8.
N7A CST-1 (S)
HO H
8 9.
P-16 CST-1 (S)
HO H
,
10.
T-10 Reactor Building HO H
(E)
11. T-13 CST-1 (SE)
HO H
8 12.
N-10-B Rad Waste (NE)
HO H
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13. MH-15 (SSI)
North Outfall HO H
Gamma
8 14. MH-18 (SS2)
East Outfall HO H
Gamma
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15. Unit 1 Dis-Diesel Bldg HO H
charge
16.
Unit 2 Dis-Diesel Bldg HO H
charge
17.
A-3 CST-2 (S)
HO H
8 18.
T-3 Reactor Bldg (N)
HO H
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8 19.
CST-2 Retention Tank HO H
20.
N9B Turbine Bldg (N)
H 0'
8H
ii.
.T-6-Diesel Bldg (E)
HO H
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22.
T-4 Diesel Bldg (E)
HO H
3 23..T-5'
Diesel Bldg (E)
HO H
8 24.
P17B-Diesel Bldg (E)
HO H
25.. T-2 opposite Gas H0
'N Recombiner
Building
26. P17A-Diesel Bldg (E)
HO 3H
27.
Py-16, CST-1 Catch Basin HO
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28.
N2A W. of Service Bldg H O
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- 29. MH-10 W of Recombiner HO H
Building
30.
PISA Turbine Bldg (W)
HO H
8 31. Py-12 CST-1 (S) -
HO H
3 32. P15B Turbine Bldg (W)
HO H
3 33. N2B W. of Service HO H
Building
34. Py-24 CST-1 (S)
HO H
3 35. T-13 CST-1 (SE)
HO H
36. CST-1 Between Pumps Soil Gamma 37. CST-1 8' w of A-1 Soil Gamma-38.
A-1 CST-1 (S)
Soil Gamma 39.
10' S of Soil Gamma 17A 40. Between Soil Gamma-P17A & T-6'
41.
CST-2 Between Pumps Soil Gamma 42. Between.
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Soil Gamma
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P17A & Pl?B 43.
CST-1 Drain 'Between' Pump's
.HO
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cCST:. Condensate Storage Tank
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