IR 05000416/1982047
| ML20054M906 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/18/1982 |
| From: | Barr K, Collins T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20054M903 | List: |
| References | |
| 50-416-82-47, NUDOCS 8207150119 | |
| Download: ML20054M906 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION f h,3(
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,C 101 MARIE T T A ST., N W., Sul T E 3100
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ATLANTA, GEOHGIA 30303 JUN 211982
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Report No. 50-416/82-47 Licensee: Mississippi Power and Light Company Jackson, MS 39205 Facility Name:
Grand Gulf Di cket No. 50-4;6 License No. CPPR-ll8 Inspection at Grand C;1f A te near Port Gibson, Mississippi i
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Inspector:
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T T. Cal ins Dat( Signed Approved by:
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_ _[ ff_[I K. P. B rr, Se on Chief Dat Signed Technical Inspection Branch Division of Engineering and Technical Programs
SUMMARY Inspection on May 24 - 27, 1982 Areas inspected
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This routine, unannounced inspection involved 28 inspector-hours on site in the areas.of liquid radioactive waste, preoperational test review, area radiation monitoring, preoperational test procedure review, previous inspector identified items and by product material license conditions review.
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Results
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Of the six areas inspected, no v1olations or deviations were identified.
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REPORT DETAILS
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1.
Persons Contacted
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Licensee Employeas
- C. K. McCoy, Plant Manager C. L. Stuart, Assistant Plant Manager
- R. R. Weedon, Chemistry and Radiation Control Superintendent
- J. C. Roberts, Start-up Engineering Supervisor T. G. Lee, Staff Health Physicist J. Vincelli,.\\cting Radiation Control Supervisor D. H. Wells Health Physics Supervisor R. Shaddix, Radwaste Supervisor D. O'Brien, Start-up Test Engineer R. M. Paley, Start up Test Engineer
- J. W. Yelverton, Quality Assurance Manager
- M.A. Lacey, Quality Assurance Consultant Other licensee employees contacted included two technicians, two security force members, and three office personnel.
NRC Resident Inspector A. G. Wagner 2. Scott
- Attended exit interview 2.
Exit Interview
'he inspection scope and findings were summarized on May 27, 1982, with tnose persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Liquid Radioactive Waste Systems The inspector reviewed the preoperational test results for the following liquid radioactive waste systems which are required to be completed as a part of Phase I testing:
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a.
1 P33 AT01 - Process Sampling System b.
1 G33 PT01 - Reactor Water Clean-up (RWCU)
c.
1 D17 PT04 - Liquid Process Radiation Monitoring The test results indicate the systems will support plant operations and the
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system meets acceptance criteria.
The inspector also reviewed SG17-PT05, Liquid Radwaste System (Discharge System) Pre-Op Test Procedure which would demonstrate the ability to transfer processed liquid waste from the floor drain or equipment drain system to the discharge basin. The inspector concluded that the pre-op test procedure appeared to be adequate; however, the results of the test will be reviewed during a subsequent inspection.
6.
Area Radiation Monitoring Systems The inspector reviewed the preoperational test results for the following radiation monitoring systems which are required to be completed as a part of Phase I testing:
a.
1 D21 PT01 - Area Radiation Monitoring System b.
1 D23 PT01 - Drywell Radiation Monitoring System The test results indicate the ;ystems will support plant operations and the system meets acceptance criteria.
7.
Inspector Followup Items (Closed)
a.
(Closed) IFI (82-21-01) - Revision to the bioassay procedure.
The inspector was informed by a licensee representative that the Bioassay Program, Procedure No. 08-S-01-32, has been revised to state that if any detectable radioactivity is indicated on a nasal swab or nose blow that a whole body count on the individual would be required.
The inspector concluded that this was adequate and had no further f
questions.
b.
(Closed) IFI (82-21-02) - Review of air sampling procedure.
The inspector was informed by a licensee representative that the Airborne Radioactivity Surveys, Procedure No. 08-S-02-52, has been revised to include the proper air sampling methods and counting techniques. The inspector concluded that this was adequate and had no further questions.
c.
(Closed) IFI (82-21-05) - ANSI qualified technicians.
The inspector reviewed the licensee's current Health Physics Staf f Organization which included the addition of sufficient ANSI N18.1-1971 qualified
technicians and the addition of first line supervisors (lead men). The L
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inspector concluded that the addition of ANSI NI8.1 qualified techni-
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l cians and first line supervisors was adequate and had rs further questions.
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d.
(Closed) IFI (82-21-06) - Health Physics Organization in disagreement
with technical specifications. The inspector reviewed the revision to
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the licensee's technical specification, Section 6.2.2 which deleted the
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number of health physicist (technicians) required for plant operation.
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The inspector concluded that the deletion of the number of health physicists (technicians) required by the technical specifications
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appeared to be acceptable as long as sufficient numbers of health
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physicists (technicians) were maintained on staff. The inspector had no further questions.
e.
(Closed) IFI (82-21-09) - Adding qualified individuals to staff. This j
item is closed. See Section 7.c above.
f.
(Closed) IFI (82-33-04) - Receipt, control, and accountability of
radioactive material.
The inspector was informed by a licensee representative that Procedure No. 08-5-01-60, Raaioactive Material
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Receipt had been revised to include the sufficient measures in
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documenting the control and accountability of licensed radioactive
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material in a timely manner. The inspector had no further questions, g.
(Closed) IFI (81-38-01) - Installation of liquid effluent monitor will i
not permit isolation valve to close in time to prevent releases. The l
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inspector reviewed the Nuclear Plant Engineering's (NPE) evaluation and
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I Technical Work Request (TWR) which concludes that NPE's analysis did result in a possible 0.4 gallon of radioactive liquid could pass the i
isolation valve before the isolation valve would isolate. A response time of less than three seconds has been determined to allow the l
isolation valve to close eliminating the possible unmonitored release
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of radioactive liquids. The inspector concluded this was adequate and had no further questions.
S.
Inspector Identified Items (0 pen)
a.
(0 pen) IFI (81-26-02) - Ventilation in Hot Machine Shop. The licensee has issued a design change request (DCR) to modify the ventilation system in the hot machine shop, however, the DCR is incomplete.
b.
(Open) IFI (81-26-03) - Ventilation and Contamination Control in Decontamination Room. The licensee has issued a design change request (DCR) to modify the ventilation system in the decontamination room, however, the DCR is incomplete.
c.
(0 pen) IFI (81-26-04) - Face velocity check for fume hoods and sample hoods.
The licensee has issued a DCR to modify the required face velocity of all fume hoods and sample hoods, however, the DCR is incomplete.
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d.
(0 pen) IFI (82-21-03) - 10 CFR 50.59, Safety Evaluation of Mobile Radwaste Solidification System (MSRR). The inspector was informed by a
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licensee representative that the required Safety Evaluation was to be performed sometime in June 1982.
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e.
(0 pen) IFI (82-21-04) - Burial allocation at Chem Nuclear Systems, Inc.
(CNSI). ; ie inspector was informed by the licensee that they are still negotiating a burial allocation with CNSI. The inspector stated this would be reviewed again upon the next inspection.
f.
(0 pen) IFI (82-21-07) - Complete testing of radwaste discharge line.
This item is addressed in Section 5.
The results of the test will be reviewed upon the next inspection.
g.
(0 pen) IFI (82-21-08) - Review results of HEPA and charcoal filter tests of the loading filters. The required tests have been completed by a contract vendor, however, the test results have not been received by the licensee. The inspector stated this would be reviewed upon the next inspection.
h.
(0 pen) IFI (82-21-10) - Radiation Protection Manager to attend a BWR training course. The inspector was informed by a licensee representa-tive that this training would be conducted in either June or July 1982.
The inspector stated this would be reviewed upon +.he next inspection.
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(0 pen) IFI (82-33-02) - Post Accident Sampling System (SPING) Effluent Monitor.
FSAR Section 18.1.27, NUREG-0737, and Safety Evaluation Report (SER) 0831 requires this system to be operable prior to fuel loading. The inspector was informed by a licensee representative this system was currently in a redesign and installation phase.
The inspector stated this would be reviewed upon the next inspection.
j.
(0 pen) IFI (82-33-03) - Adequate shielding on liquid sample lines of post accident sampling system.
The inspector was informed by a licensee representative that the ALARA Committee had reviewed this problem and determined that shielding the existing sample lines would be sufficient rather than re-routing the sample lines to reduce radiation exposure in the event of an accident. The inspector stated this would be reviewed upon the next inspection.
9.
By-Product Radioactive Material License The licensee's By-Product Radioactive Material License No. 23-19573-01, authorizes the possession of five curies of Hydrogen-3 for the use in performing cooling water tracer studies.
The inspector reviewed the conditions of the license. The inspector stated that the licensee appears to meet all described conditions. The inspector had no further questions.
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10.
10 CFR 19.11 requires, in part, that each licensee post current copies of l
Form NRC-3, Notice to Employees, in a sufficient number of places to permit
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individuals engaged in licensed activities to observe them on the way to or from any licensed activity location. The inspector observed the posting of
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notices required by 10 CFR 19.11 and had no further questions.
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11.
General Employee Training (GET)
l The inspector reviewed specific sections of the employee handout (study guide) for general employee training (GET) which included, Emergency Plan and Procedures, Site Security Program, General Description of Plant and Facilities, Industrial Safety Program, Quality Assurance Program, and Radiation Worker Training. The inspector stated that the handout material appeared to be adequate and had no further questions.