IR 05000263/1976010
| ML20024G188 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 06/29/1976 |
| From: | Jackiw I, Little W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024G184 | List: |
| References | |
| 50-263-76-10, NUDOCS 9102070661 | |
| Download: ML20024G188 (7) | |
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UNITED STATES NUCLEAR RECULATORY COMMISSION
OFFICE OF INSPECTION MiD ENFORCEMENT
REGION III
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Report of Operations Inspection IE Inspection Report Nc.. 050-263/76 10 Licensee:
Northern States Power Company 414 Nicollet Hall Hinneapolis, Minnesota $5401 Monticello Nuclear Generating Plant License No. In'R-22 Honticelle, Minnesota Category:
C Type of Licensee:
BWR GE'1670 MWt Type of Inspection:
Routine, Unannounced Dates of Inspection:
June 14-17, 1976
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Principal Inspectorr
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Accompanying Inspectors:
None Other Accompanying Personnel: None p
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Reviewed By:
W. S. Li e, Chief
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Nuc1 car Support Section
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9102070661 760701 PDR ADOCK 05000263 O
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SUMMARY OF F1:lD1NCS i
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Inspection Summary (
Inspection on June 14-17. (76-10):
Reviewed organization and adminis-tration, training, and operator requalification training.
Enforcement items None.
Licensee Action on Previously identified Enforcement items None reviewed.
Other Significant items A.
Systems and Components Following a shutdown to repair "A" relief valve, the plant was started up on June 16, 3976 and the torus test program was resumed.
Preliminary test results indicate that no major prob-Icms extr.t.
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B.
Facility items (Plans and Procedures)
None.
I C.
Manager':i1 items The licensee has implemented several organizational changes.
Mr. L. R. Eliason has been appointed the Plant Manager.
Mr.
F. L. Fey has been appointed the Radiation Protection Engineer.
D.
Noncompliance Identified and Corrected by Licensee None.
E.
Deviations None.
F.
Status of Previously Rcported Unresolved items Nonc reviewed.
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,Mannnement Interview
At the conclusion of the inspection on June 17, 1976, an exit 1 terview
9 was conducted with Mr. Eliason and other members of his staff. The
following items were discussed.
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A.
The inspector stated that the licensee's organizational structure
is in accordance with the Technical Specifications.
(Paragraph ?,
Report Details)
.B.
The inspector.noted that a number of organizational changes had been initiated by the licensee.
(Paragraph 2, Report Details)
C.
The inspector stated that the training and requalification train-ing programa were reviewed. No problems were identified in these areas.
(Paragraphs 3 and 4, Report Details)
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REPORT _ DETAILS i
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1.
Persons Contacted L. E11ason, Plant Manager H. Clarity, Superintendent, Plant Engineering and Radiation Protection W. Anderson, Superintendent, Operation and Maintenance J. Panch Training Supervisor 11. Kendall, Plant Of fice Supervisor F. Fey, Radiation Protection Engineer W.11111, Engineer, instruments P. Pochop, Quality Orcup 2.
Organir.ation and Administration the inspector reviewed the licenree's onsite and of fsite organ-irations to ascertain whether they are in accordance with the requirements of the Technical Specifications. The following items were considered during this review: onsite organization structure; personnel qualification levels; specification of duthoritica and responSibilitiesi and shift crew CompoDition.
The f ollowing items were confirmed by the inspector:
The licensee's onsite organization structure is described a.
in Administrative Control Directive (ACD) 3.1.
b.
Ncndestructive Test personnel qualifications are in accord-k ance with the licensee's requirements.
Key management personnel of the station meet the requirements of ANSI 18.1.
Authorities and responsibilities of supervisory personnel are c.
delineated in ACD 3.1
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d.
Safety Audit Committee and Operations Committee memberships and qualifications are in accordance with Technical Specificctions.
Also, ACD 3.2 provides a written charter for the functior,ing of the Operations Committee.
The minimum shif t crew composition is in accordance with the e.
Technical Specifications.
f.
Mr. L. Eliason has assumed the position of Plant Manager.
llis replacement to the position of Radiation Protection is Mr.
F. Fey.
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3.
Training I
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Overall training activities for new employees and retraining for nonlicensed personnel were reviewed to ascertain whether l'
they are in conformance with i tchnical Specifications and licensee's procedures. The following itets were considered during this reviews establishment of a fonial training and retraining program for new employees, tempo *ary employees, nonlicensed/ licensed personnel, technicians and craft personnel; the training program covers administrative controls, raiiological health and safety, industrial safety, security, emergency plan, and quality assurance training; the retraining program includes on-the-job training and fire prevention training; the periodic evaluation of the training
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and retraining programs; and prenatal radiation exposure instructions are provided to female employees.
The inspector observed the followings
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ACD 3.13, establishts training requirements for new employees, a.
temporary employees and general plant employees. Annual training is provided to all plant employees.
New employee indoctrination is conducted within 30 days of employment.
b.
Annual training for all plant personnel covers the following areat (1) Emergency Plan and Procedures, (2) Radiological llcalth and Safety, (3) plant Controlled Access Areas and Security Procedures, (4) Industrial Safety and First Aid, and (5)
Use of Protective Clothing and Equipment.
I Instrument and Control and Radiation Protection personnel c.
participate in specialist trainee progression programs.
These programs consist of two parts.
Part one is the formal training portion and part two is the on-the-job training portion.
Records of on-the-job training is maintained by the section supervisors.
The inspector noted that although formal training req tire-ments exist for maintenance personac1, no formal program had
been established to document on-the-job activities performed
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by these individuals.
d.
A system exists for training programs to be evaluated by means
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oft (1) written examinations, (2) oral examinations and quizzes and (3) practical examinations or demonstrations.
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In regard to instruct'ing female workers about prenatal exposure risks, the licensee stated that tne general employee training
program will be upgraded to include this subject, b,
The regulatory position is stated in Regulatory Guide 8.13 Revision 1.
4.
Requalification Training
.The licensed operator requalification training program was reviewed to ascertain whether it is effective and in conformance with Regulatory requirements.
The following was confirmed by the inspectors A preplanning Iceture schedule has been-established..
j a.
b.
Attendance is being documented, c.
Train'.ng aids used in lieu of an instructor are specified in the schedule.
d.
On-the-job training requirements are specified and include -
the followings (1) control manipulations, (2) review of significant facility design, procedural and licensing changes, (3) review of integrated operating. procedures, (4) review of abnormal and emergency operating procedures,
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(5) review of abnormal occurrences and unusual events, and-
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(6) review of administrative matters of significance to operating personnel.
e.
Records of three licensed individuals were reviewed and included the followings (1) examinations with answers, (2). documentation of manipula*: ions. - (3). documentation of I
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simulated drills, (4) evaluations of examinations, (5)
accomplishment of self study, and (6) accelerated retraining I
as applicable.
5.
Torus Testing
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On June 14, 1976, the licensee attempted to actuate safety relisf valve
"A".
After several attempts the valve was declared inoperable and the plant was shutdown.
The cause of failure of safety relief l
valve "A" was determined to be the malfunction of an air solenoid
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volve.
Follbwing replacement of the defective air solenoid valve,
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the plant was started up and torus testing resumed on June 16, 1976.
i Paoliminary test results of singic valve actuations, sequential
valve actuations and multiple valve actuations appear to be within expected limits.
No major problems evolved during the (
test.
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