IR 05000245/1979003
| ML19289F634 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/16/1979 |
| From: | Crocker H, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19289F624 | List: |
| References | |
| 50-245-79-03, 50-245-79-3, 50-336-79-03, 50-336-79-3, NUDOCS 7906150213 | |
| Download: ML19289F634 (6) | |
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U.S. NUCLEAR REGULATORY C0FESSION OFFICE OF INSPECTION AND ENFOR;EMENT Region I 50-245/79-03 Report No. 50-336/79-03 50-245 Docket No. 50-336 OPR-21 License No. DPR-65 Priority Category C
Licensee:
Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06101 Facility Name:
Millstone Units 1 and 2 Inspection at:
Waterford, Connecticut Inspection conducted:
February 12-15, 1979 Inspectors: [I P. d. iN M_
' -t < '7 9 G. P. Tuhas, Radiation Specialist date signed J
date signed date signed Approved by-JA M 3 // /, [y 9'
H. W. Crocker, Acting Chief, Radiation
/ 'date s'igtie'd Support Section, FF&MS Branch Inspection Summary:
Inspection on February 12-15, 1979 (Report Nos. 50-245/79-03 and 50-336/79-03 Areas Insoected:
Routine, unannounced inspection of the Radioactive Waste Management System during operations including:
liquid and gaseous radioactive effluent releases; radioactive effluent records and reports; effluent control instrumentation; reactor coolant water quality; and, followup on previous inspection findings.
Upon arrival at 6:30 p.m., February 12, 1979, areas where work was being conducted were examined to review radiation safety practices and procedures.
This inspection involved 15 inspector-hours on site for each unit by one NRC regional based inspector.
Dr. William D. Travers of the Office of Nuclear Reactor Regulations, Effluent Treatment Systems 2229 153 Branch, accompanied the inspector.
Results: Of the five areas inspected, no items of noncompliance were identified in four areas; one item of noncompliance was iden-tified in one area (Deficiency - failure to post a radioactive materials storage area as required by 10 CFR 20.203(e), Paragraph 7).
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DETAILS 1.
Persons Contacted
- J. F. Opeka, Station Superintendent
- E. J. Mroczka, Station Services Superintendent
- A. G. Cheatham, Health Physics Supervisor R. Brisco, General Services Supervisor V. Jones, Chemist, Unit 1 R. Langer, Chemist, Unit 2
- denotes those present during the exit interview conducted by telephone on February 21, 1979.
The' inspector also talked with and interviewed several other licensee employees, including members of the Health Physics and Operations staff.
2.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance (50-245/78-12-01):
Failure to change the stack sample cartridge at the frequency required by Technical Specification 4.8.A.2.(b).
Surveillance Procedures 814/2814,
" Weekly Sampling and Analysis of the Unit 1 Stack and the Unit 2 Vent for Iodine-131," and 816/2816, " Unit 1 Stack and Unit 2 Vcnt Weekly Particulate Filter Sampling and Analysis for Principle Gamma Emitters," have been revised to insure that the requirement of Section 4.8. A.2.(b) is met.
(Closed) Noncompliance (50-245/78-12-02):
Failure to determine gross alpha activity on each batch of liquid effluent as required by Technical Specification 4.8.C.2.
Unit 1 Chemistry Procedure 809A, " Identified Liquid Waste Discharge," was revised June 26, 1978 to insure the gross alpha determination is made.
(Closed) Noncompliance (50-245/78-12-03):
Failure to sample reactor coolant for conductivity and chlorides every four hours on startup as required by Technical Specification 4.6.C.2.
In a letter datea June 27, 1978 (MP-S-898), the Chemistry Supervisor informed appropriate personnel of the necessity to perform the required analysis.
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(Cinsed) Noncompliance (50-245/78-24-03, 50-336/78-21-03):
Failure to perform an audit of areas of the Techncial Specifications as required by Section 6.5.3.8.(a).
The Nuclear Review Board (NRB) Audit Procedure was revised September 29, 1978 to explicitly require an annual audit of the Radiation Protection Program.
(Closed) Noncompliance (50-366/78-21-04):
Failure to report results of NRB audits within the time period specified in Tech-nical Specification 6.5.3.10.(c).
The preliminary results of the (Jnit 21978 NRB audit was reported to management on August 30, 1978.
The NRB audit procedure was revised September 29, 1978 to insure that responsible management representatives are informed of audit findings inan expeditious manner consistant with Tech-nical Specification requirements.
(Closed) Noncompliance (50-245/78-12-05, 50-336/78-12-01):
Failure to maintain records as required by 10 CFR 71.62.
The licensee has revised his procedures for shipment of radioactive material to specifically require documentation of the cask model number and identification. A review of those shipments of greater than Type A cuantities indicate the procedures are being followed.
(Closed) Previously Identified Item (50-245/78-39-06, 50-336/78-36-01 ):
Calibration and operability of portable radiation instru-mentation. The licensee has revised Health Physics Procedure HPP 904/2904, " Calibration of Health Physics Instruments." This revision, dated January 11, 1979, provides adequate instruction to insure the portable radiation instrumentation is capable of performing its intended function.
In addition, extensive revision of procedures HPP 904/2904A and B are in progress to upgrade calibration of other health physics related equipment. After removal from service, the licensee was able to recalibrate all Teletector survey instruments and return them to use.
Three PIC6A instruments could not be recalibrated and have been returned to the vendor.
3.
Liquid and Gaseous Radioactive Effluent Releases The inspector examined the licensee's radioactive effluent releases against the requirements of the following specifications:
Appendix A to License No. DPR-21, Section 3.8, Radioactive
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Materials, Limiting Condition for Operation and Section 4.8, Radioactive Materials, Surveillance Requirements.
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Appendix B to License No. DPR-21, Section 2.4, Radioactive
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Effluents.
Appendix B to License No. DPR-65, Section 2.4, Radioactive
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Effluents.
This examination covered the period May 1978 through January 1979.
Implementation of the augmented off gas treatment system has substantially reduced the airborne effluents from the facility.
No items of noncompliance were identified in this area.
4.
Radioactive Effluent Records and Reports The inspector reviewed about 25% of the records for the period May 1978 through January 1979 to determine compliance with Tech-~
nical Specifications and procedural requirements.
The areas covered by these requirements are listed below:
Airborne Releases:
Monthly off-gas isotopic analysis
Monthly H, Sr89, and gross alpha Daily gaseous effluent reports Weekly iodine and particulate analysis Activity determination of Waste Gas Stroage Tanks Containment Purge Release gama emitters Monthly Unit 2 Condenser Air E,iector gama emitters Quarterly composite for Sr90 particulates.
Liould Effluents:
Liouid discharge permits Unit 2 steam generator blowdown, monthly analysis for Sr89, Sr90, H, and dissolved gases, and weekly analysis for gamma
emitters Monthly composite of liquid waste tanks for H, Sr90, and
gross alpha Determinations of curie content in liquid waste tanks.
Unmonitored release path sample analysis.
The " Semi-Annual Radioactive Effluent Release Reports" submitted for Units 1 and 2 for the first half of 1978 were reviewed. The reports were consistent with data available at the facility and with the requirements of Technical Specification, Appendix B, Section 5.6.1.b.
No items of noncompliance were identified in this area.
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5.
Effluent Control Instrumentation Testing and calibration of effluent control instrumentation was reviewed against the requirements of Unit 1 Technical Specification Table 4.2.1, Unit 2 Technical Specification Table 4.3-3 and Sections 2.4.1.3 and 2.4.2.3 of Appendix B, and the licensee's instrumentation and control procedures.
6.
Reactor Coolant and Water Quality Records of periodic tests, chemical, and radioactivity control were reviewed for the period April 1978 through January 1979 to determine compliance with the following requirements:
Appendix A to License No. DPR-21, Section 3.6.C, " Coolant
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Chemistry."
Appendix A to License No. DPR-65, Section 3.4.7, " Reactor
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Coolant System Chemistry."
No item of noncompliance was identified in this area.
7.
Facility Tour During a tour of the Unit 2 Auxiliary Building on February 12, 1979, the inspector observed that access to the 38' 6" elevation was controlled by locked gates and posted as a radiation area.
The 38' 6" elevation contains the spent fuel storage pit and new fuel storage vault.
At the time of the tour the new fuel storage vault contained quantities of radioactive material in excess of 10 times the value specified for that material in Appendix C of 10 CFR 20.
The spent fuel storage pit also contained quantities of radioactive materials in excess of 10 times the values specified in Appendix C.
10 CFR 20.203, " Caution signs, labels, signals, and controls" states:
"(e) Additional requirements.
(1) Each area in which licensed material is used or stored and which contains any radio-active material (other than natural uranium or thorium) in an amount exceeding 10 times the qE3ntity of such material specified in Appendix C of this part shall be conspicuously posted with a sign or signs bearing the radiation caution symbol and the words:
CAUTIONI RADI0ACTIVEMATERIAL(S)."
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The new fuel storage vault was not posted with a " Radioactive Materials" sign nor was the access gates to the 38' 6" and spent fuel pit area.
This finding represents an item of noncompliance with 10 CFR 20.203(e) (50-336/79-03-01).
7.
Exit Interview The inspector met, by telephone, with the licensee representatives (denoted in Paragraph 1) on February 21, 1979.
The inspector summarized the scope and findings of the inspection as presented in this report.-
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