IR 05000282/1979024
| ML19211D013 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 11/26/1979 |
| From: | Dubry N, Fisher W, Hueter L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19211D011 | List: |
| References | |
| 50-282-79-24, 50-306-79-20, NUDOCS 8001160110 | |
| Download: ML19211D013 (13) | |
Text
.
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-282/79-24; 50-306/79-20 Docket No. 50-282; 50-306 License No. DPR-42; DPR-60 Licensee: Northern States Power Company 414 Nicollet Hall Minneapolis, Minnesota 55401 Facility Name:
Prairie Island Nuclear Generating Station, Units 1 and 2 Inspection At: Prairie Island Site, Red Wing, MN Inspection Conducted: October 10-12, 1979 W8HwL
//-21-77 Inspectors:
L. J. Hueter
N. E. dub,ry
// - 86 - 7 /
fl k%
II - 86 ' h Approved By:
W. L.
1 sher, Chief Fuel Facility Projects and Radiation Support Section Inspection Summary Inspection on October 10-12, 1979 (Report No. 50-282/79-24; 50-306/79-20)
Areas Inspected: Routine, unannounced inspection of the radiation protec-tion program, including:
qualifications; audits; training; radiation protection procedures; instruments and equipment; exposure control; posting, labeling, and control; surveys; notifications and reports; IE Bulletin 79-19; IE Circular 79-09; IE Information Notice 79-08; review of licensee actions on Radiation Area Monitors identified in Reports 78-05 and 78-07; handling of the noncompliance item from Report No. 79-03; contract radiation technician qualifications; and a review of licensee actions during the recent tube rupture (October 2, 1979). The inspection involved 55 inspector-hours on site by 2 NRC inspectors.
Results: No items of noncompliance or deviations were identified.
8001100 1756 253
.
'
DETAILS 1.
Persons Contacted
- F.
P. Tierney, Jr., Plant Manager
- D. A. Schuelke, Superintendent of Radiatfsn Protection R. A. Stenroos, Assistant Radiation Prot:ction Supervisor
- A.
C. Johnson, Radiation Prctection Coo: linator
- J. T. Linville, Plant Chemist
- C. D. Feierabend, NRC Resident Inspector K. G. Delong, Radiation Protection Specf41ist L. E. Finholm, Training Supervisor The inspectors also talked with other licensee employees, including members of the technical staff and contract personnel.
- Denotes those present at exit interview.
2.
General This inspection began at 7:45 a.m. on Getober 10, 1979, with subsequent tours and observations, in',1uding:
access control, radwaste and auxiliary buildings and Unit I containment. Special emphasis was given to the radiatior, protection program functions during the October 2, 1979, failure of a Unit 1 steam generator tube. Housekeeping, observed during the plant tours, appeared adequate. During the tours the inspectors made independent survey measurements, using licensee's meter (Teletector No. 14389, calibrated August 1979). Measurements made during the tours were in agreement with posted survey data.
3.
Licensee Actions on Previous Inspection Findings Procedure PINGP 128, Revision 4, was implemented February 2, 1979.
This procedure provides daily records of airborne surveys by the seven continuous air monitors (CAM). Revision 4 designate the CAM 1979, revealed no problems.y records from February 1979 to October 10, locations. A review of the A review of the Area Radiation Monitors found the Circulating Water Discharge Liquid Monitor System (R-21) was modified and returned to operation in April 1979. No further problems have been identified with this monitoring system.
(Closed) Infraction (50-282/79-03):
Corrective actions were reviewed concerning a previous noncompliance item. The licensee had ascertained that the vendor had completed cask repairs.
1/
IE Inspection Rpt No. 50-282/79-03 and No. 50-306/79-03-2-1756 256
.
.
The inspector also reviewed drawings and revisions 2/ made to the cask certification and found no problems. There are no further questions regarding this matter.
No items of noncompliance or deviations were identified.
4.
Radiation Protection Organization and Qualifications Theradiationprotectiongroup'sorganizatj7nalstructureisas described in a previous inspection report.-
There have been no changes in key supervisory personnel in the past year. The position ofRPCoordinator-Chemistry,vacgytatthetimeofthelast radiation protection inspection,- has been filled by a Radiation Protection Specialist with about six years experience at the facility. Also since the last referenced inspection, one of the two Radiation Protection Engineers has been replaced. The new individual has a degree in Civil Engineering and two years previous nuclear experience. These two engineers are responsible for the radwaste system.
Radiation Protection coverage is provided by the radiation protection organization seven days per week on day shift and five days per week on swing shift. Shift Supervisors and Reactor Operators are trained and qualified in radiation protection procedures to take the necessary radiation protection actions until thearrivalofHeagphPhysicspersonnelasdescribedinaprevious inspection report.-
The licensee continues to contract with Nuclear Support Services (NSS) for health physics assistance during refueling outages and on other occasions as needed.
Regarding requirements and assignments of contract radiation technicians, the licensee requires contract rad techs to have prior working experience and to submit a resume before coming to the Prairie Island site. A review of NSS procedures for health physics technician training and qualification appears to be adequate. The licensee stated he assigns the junior technicians to work in the turbine, auxiliary, and radwaste buildings; and the senior technicians to work in containment. The licensee uses their own personnel for coordinators and supervisors. No problems were found in this area.
2/
Cask Certicate of Compliance No. 6244, Rev. 3 (7-30-79)
3/
IE Inspection Rpt No. 50-282/78-18.
4/
Ibid.
5/
Ibid.
_.
-3-1756 257
.
5.
Audits
.
The Safety Audit Committee's (SAC) Audit No. P-78-2 covering the time frame of November 1978 to December 1978 was reviewed. An audit conducted November 1-3, 1978, covered the subjects of As Low As Reasonably Achievable (ALARA) with respect to radiation exposures and releases of radioactive materials. The audit appeared to be reasonably comprehensive. No significant problems were identified by the audit.
No items of noncompliance or deviations were identified by the inspectors.
6.
Training The inspectors did not attend the General Training, Radiation Protec-tion Training and Respiratory Protection Training sessions during this inspection. These sessions provide the initial instruction to new employees and visitors and the annual retraining. Th essions had been attended and reviewed in detail in November 1978 Records of initial training and/or annual retraining were reviewed for several people selected by the inspector at random from among both contractor and company employees. Records were available for all personnel selected and no problems were identified.
The training and qualification program for radiation protection per-sonnel consists of a weighted point system with wage rates being tied to the point total.
Part is based on formal training which is the individual's responsibility; part is based on on-the-job training under the supervision of a senior technician, who signs a qualification card at completion.
Retraining of radiation protection personnel is provided by weekly training sessions on pertinent subjects by the radiation protection coordinators, except during outages and heavy work loads.
A review of records of these training sessions for the nine months of 1979 showed that 30 sessions were held with those in attendance generally Imbering about twelve. Subject matter included review of administra-tive control directives, review of chemistry procedures and labora-tory techniques, and various other appropriate subjects.
Refer to paragraph 4 regarding training of contract radiation technicians.
No items of noncompliance or deviations were identified.
6/
Ibid-4-1756 258
.
7.
Radiation Protection Procedures The Radiation Safety Manual (RSM) was reviewed for completeness and new changes. There apparently have been no changes in the RSM since it was revised in it's entirety October 30, 1978. The RM was reviewedduringthelastradiationprotectioninspection.yj (see paragraph 9 b)
The inspector noted that use of a hood, in the licensee's respirator program will require that the narrative and attachment C of the RMS be updated. This matter was discussed at the exit interview.
Since the last radiation protection inspection, a number of revisions had been made to Section Work Instructions in Radiation Protection (SWI-RP).
The following SWI's were reviewed during this inspection.
SWI-RP-3 Revision 5, Jan. 18, 1979
" Radiation Work Permit /
Exposure Control" SWI-RP-4 Revision 17, Feb. 23, 1979
" Work Assignments" SWI-RP-12 Revision 1, Jan. 5, 1979
"Special Training Program to Satisfy T.S. 6.1.D."
SWI-RP-13 Revision 4, Jan. 22, 1979
" Tool and Equipment Control in Controlled Areas" SWI-RP-15 Revision 2, Feb. 1, 1979
" Radioactive Component Control" SWI-RP-22 Revision 2, Feb. 1, 1979
"TLD Reader and Chip Calibration" These procedures appeared to be compatible with technical specifications.
No items of noncompliance or deviations were identified.
8.
Instruments and Equipment A review of calibration dates and records from December 1978 to the present was conducted for portable and fixed devices. The inspector observed that a number of portable devices were taken out of service since the last inspection and that a number of Work Requests (WR'S)
were issued for instruments needing repair. Further investigation showed a long time lapse between issuance of a WR for a meter and 7/
Ibid 1756 259-5-
- the repair and return of the meter to service.
At the beginning of the inspection 5 of 8 frequently used portable survey instruments were in for repairs.
By the end of the inspection 7 of 8 of these instruments were out of service.
The status of area radiation monitoring instruments and equipment was reviewed. The inspector specifically looked at R-21, Circ Water Discharge Canal Liquid Monitor; 1R2 and 2R2, Containment Vessel Area Monitor; and the state of R43-R47 area monitors on the new condensate polishing system. The licensee indicated that the Circ Water Discharge Canal Monitor system had been modified and put in service in April 1979. (paragraph 3)
A review of the monthly functional tests, Test 1028, from February 1979 to September 1979, found 1R2 and 2R2 usually in need of repair. At the time of this inspection IR2 was working and 2R2 was awaiting parts on order.
Licensee representatives ind'cated that parallel monitoring systems are on order for the Contaimaent Vessel Area Monitor, which will be capable of measuring 1.0E-08 Rad at the surface. For monitors R43-R47 the detector assemblies and tubes have been on order but to date only the tubes have been received. The system into which these monitors are to go is still under construction.
These matters were discussed at the exit interview.
No items of noncompliance or deviations were identified.
9.
Exposure Control a.
External Exposure External radiation dose to beta gamma radiation is based on monthly supplied vendor TLD; dose to neutron radiation is also based on vendor supplied TLD. The neutron sensitive TLD's are issued to those using a neutron source for instrument calibration and personnel entering reactor containment during power operation.
The neutron badges are then processed and read at the end of the month.
The licensee continues the use of dosimeters and their own added TLD's for exposure control purposes between the monthly badge periods. A daily alert list is obtained from the computer for any individual exceeding 1000 mrem dose for the calendar quarter on daily exposure input from dosimeter reading cards.
No problems were observed in c, review of the external exposure control dose records of 1978 and the dose records for the first eight months of 1979. The highest individual whole body dose received in 1978 was about 3000 mrems, and through August 1979 the highest whole body dose received was about 1540 mrem. Skin-6-1756 260
.
and extremity doses have not been appreciably above whole body
-
doses. The total neutron dose received at the site during the first eight months of 1979 has been about 820 or an average of 100 mrem per month. The highest neutron dose received by an individaul during a calendar quarter in 1979 has been 66 mrem and in the year-to-date (as of August 31st) has been 96 mrem.
The total dose received onsite in 1978 was about 197 man-rems, which appears to be a very good achievement considering both units had a refueling outage during the year.
In 1979 as of this inspection the accumulated dose was about 150 man-rems.
To meet requirements of 20CFR20.102(a) as amended August 20, 1979, regarding exposures of short-term workers or moonlighters, the licensee requires part time N.S.P. employees to fill out and sign a form showing any exposure received at other than the licensee's facility,during the current calendar quarter. As an added precaution, an updated form is required to be signed by these workers when their dose at N.S.P. reaches 300 mrem increments during the quarter.
b.
Internal Exposure Internal exposure from tritium is evaluated by quarterly urinalysis for individuals who have potential for exposure to tritium.
A review of records for the first three quarters of 1979 found the maximum body buden of tritium to be about 1.0%.
The sampling period continues to be staggered such that about one third of the samples are collected and analyzed each month.
Internal exposure from gamma emitters was determined by whole body counting using a Helgeson "do-it yourselt" whole body counter. The inspector's review of whole body count data from November 2,1978, through August 30, 1979, identified no problems. The licensee's evaluations of whole body counts were adequate to ensure compliance with the airborne exposure criteria of 10 CFR 20.103. No airborne exposures greater than 520 MPC-hours were identified. Further, no individual exceeded the 40 MPC-hour control point.
Some elevated initial counts were found to be due to minor external contamination.
Lower counts were obtained after a shower was taken.
The inspectors verified that the respiratory protection program essentially remains as described in a previous inspection report.8/.
It was noted that the licensee has added another respirator to their program.
It is the Defense Apparel Hood HSQ-10-1100, NIOSH approval 19C-120, for which a protection factor of 1000 will be taken (see paragraph 7).
During the inspection tours it was noted that signs specifying the required regulator pressures were posted at the permanent respirator manifold locations.
8/
Ibid-7-1756 261
.
The licensee recently changed their method of respiratory quali-
-
fication tracking. They utilize a computer printout which lists the name, social security number, security badge qualification, date of medical exam, date of written exam, and the masks for which the individual is qualified.
No items of noncompliance or deviations were identified.
10.
ALARA ALARA (As Low as Reasonably AcLievable) efforts were apparent in the following areas:
a.
ALARA continues to be considered in writing Radiation Work Permits (RWPs)
b.
Installed shielding for the reactor coolant drain tank pump piping.
c.
Installed cement shielding blocks at the ADT collection tanks and throughout the Unit 2 thimble chase area.
d.
Replacing a manual valve with a control valve in the Waste Hold-Up Tank Room, a high radiation area.
e.
Installing a grating between the barrel isles in the waste solidification facility tc allow deconning.
f.
Installed a T.V. camera to remotely observe eddy current testing.
g.
Initiated a system for tracking sources of exposure during refueling outages to identify areas where efforts to reduce exposure would be most effective.
h.
Initiated the removal of short length control rods in the fuel pit.
i.
Designed, fabricated and implemented the use of some automated equipment for reactor head removal and stud bolt cleaning.
j.
Changed procedure for the placement of thimble plugs in new fuel before refueling.
k.
Held meetings with engineers during the design stage of new systems or modifications to minimize the time and exposure in radiation areas on projects such as: 1) preventive maintenance and repair on the spent fuel transfer system and 2) modifications to the pipe rupture restraint system.
1.
Used mock-ups and training before actual work, such as changing reactor coolant pump seals.
-8-1756 262'
.
m.
Instructed to change out filters before working on lines in the area near filters.
n.
Halved the number of routine surveillance containment entries.
o.
Conducted outage meetings several months in advance of planned outages to determine H.P. manpower needs and to evaluate means to reduce exposure for various jobs before work begins.
Other efforts also have been made. The success of the licensee's efforts are apparent in terms of the low external dose received over the past several years when compared to other facilities, as well as their trend toward lower levels for the past several years. Refer to paragraph 9.a for details of external exposure data.
No items of noncompliance or deviations were identified.
11.
Posting, Labeling, and Control Controlsareessengallyunchangedfromthosedescribedinaprevious inspection report.
.
Posting, labeling, and implementation of controls were observed during inspection tours described in Paragraph 2, with no significant problems being identified.
RWP's were reviewed from the time of the last radiation protection inspection with emphasis on those RWPs generated for the present outage associated with the steam generator tube rupture.
It appeared that RWPs were initiated timely, were properly approved, and required adequate radiation protection measures.
The procedures for control and reuse of tools w g fixed contamination is the same as identified in a previous report No items of noncompliance or deviations were identified.
12.
Surveys Daily and special general area survey records for contamination and direct radiation were reviewed for January 1979 to October 11, 1979.
Emphasis was placed on the refueling outage, April 1979, and the recent S/G tube rupture, October 1979. When elevated levels of radiation or contamination were identified, follow-up action appeared proper and timely.
Daily records of airborne surveys from the Continuous Air tionitors (CAM)
were reviewed from February 2, 1979, to October 11, 1979.
Portable air sample survey records were also reviewed.
9/
Ibid 10/
Ibid-9-1756 263
.
No items of noncompliance or deviations were identified.
13.
Notifications and Reports According to licensee personnel and substantiated to the extent of records reviewed by the inspectors, the licensee has experienced no theft, loss, releases, concentrations of radioactive material, or overexposure of personnel requiring report jarsuant to 10CFR20.402, 20.403, or 20.405, or other reporting requirements.
A random sampling of employee records showed that reports of personal exposure are being submitted to the Commission as required by 10CFR 20.408 for terminated employees and to individuals upon request, as required by 10CFR19.13 The inspectors requested their calculated dose upon leaving the site.
This dose was provided in accordance with 10CFR19.13(e).
No items of noncompliance or deviations were identified.
14.
Circulars Regarding IE Circular No. 79-09, " Occurrence of Split or Punctured Regulator Diaphragms in Certain Self-Contained Breathing Apparatus,"
the licensee tested the regulators according to the enclosure. No problems were found.
IE Circular No. 79-15, which addressed a similar problem, does not apply to this licensee, who does not use the referenced breathing apparatus.
No items of noncompliance or deviations were identified.
15.
Bulletins The licensee addressed IE Bulletin No. 79-19," Packaging of Low-Level Radioactive Waste for Transport and Burial," in a letter to the Commission on September 21, 1979. A review of the nine specific items addressed by the bulletin showed that: a current set of NRC and DOT regulations are maintained by the licensee; current copies of burial firm licenses are on hand; organizational responsibilities are defined; approved procedures and instructions are provided to appropriate personnel (it was noted the licensee has rechecked approximately 400-500 drums of compacted waste to ensure no liquid was present); records indicated the Radiation Protection Group had been trained in DOT and NRC regulations and burial license requirements for radioactive material shipment in 1978, but 1979 annual retraining is still due; and Prairie Island uses a cement solidification method for liquid low-level radioactive waste.
- 10 -
1756 264
.
Three items addressed by the bulletin >ill be looked at in future inspections. The revision to the General Employees Training Program (provided annually) will be reviewed for inclusion of training needed by employees regarding radioactive material shipments. The training supervisor plans to have the revision completed no later than March 1980.
The development of a retraining program for operations nersonnel has not been addressed yet; this matter was discussed ao the exit interview. The results of the management audit performed on September 12, 1979, were not available for review.
Conversation with the Quality Engineering staff revealed the handling and shipping of radioactive material is receiving additional attention since the issuance of IE Bulletin No. 79-19.
No items of noncompliance or deviations were identified.
16.
I. E. Information Notices. No. 79-08 The licensee reviewed with the inspector the interconnection of contaminated systems with service air systems used as the source of breathing air. The station air is cross-connected with service air and is separated by three isolation valves. At present there appears to be no line draining capability. The licensee will review this situation because of the tube rupture.
It was noted that HEPA filters are on lines before the hose manifold connections. The licensee stated he may consider putting water traps at low points in the station air system lines or the condensate filter demineralizer lines as additional precaution.
No problems were found in this area.
17.
Steam Generator Tube Rupture The inspectors reviewed the health physics records which pertain to the Steam Generator tube rupture of October 2, 1979.
The following information was reviewed:
-
Unit 1 primary coolant had been sampled at 0734 on morning of the event; no problems were noted.
Weekly steam generator chemistry had been done on October 1, 1979
-
with no problems noted.
-
Unit 1 Steam Generator tube rupture occurred at 1414.
-
Within 15 minutes of the alarm a marinelli gas sample had been collected from the air ejector.
- 11 -
1756 265
.
'
-
Additional air ejector gas samples were collected at 1513, 1620, 1650, 1730, and approximately every half-hour until 0730 on October 3, 1979, when the air ejector was secured.
The above results were integrated for the period of the release
-
and approximately 30 curies of noble gas were discharged.
-
Tritium analysis and calculation (temperature corrected) indicate approximately 2E-5 curies were released.
-
Air Sample data from the turbine building sump indicated approximately 0.02 curies of noble gas were released via this source.
Based on worst case assumptions, the estimated release of noble
-
gas via the steam dump was about 0.1 curie.
Licensee calculations indicated offsite exposure rates at the site
-
boundry, 595 meters from the reactor, to be 0.1 - 0.2 mR/hr peak during the first hour yeilding a maximum whole body dose of 0.07 mrem for the entire incident.
Analyses of samples by the licencee indicate no measureable iodine
-
was released.
-
General area radiation and smear surveys within the plant were started at approximately 1700 on October 2, 1979.
-
The initial Unit 1 containment entry was made at 1330 on October 3, 1979. The highest smearable activity (opposite the pressurizer relief tank) was about 8500 dpm/100 square centimeters.
General fields of 1.5 mR/hr gamma and 30 mrad /hr beta were measured.
Recovery operation records which include inspection of the steam generator were reviewed. Radiation work permits (RWP's), surveys, and ALARA considerations appear adequate.
The review of records and obervations made during the inspection indicate that the licensee aggressively addressed the tube rupture incident and demonstrated a high degree of health physics professionalism.
No items of noncompliance or deviation were identified.
18.
Exit Interview
' lite inspectors met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection. The inspectors summarized the scope and findings of the inspection.
- 12 -
1756 266
.
'
a.
The inspectors stated that no items of noncompliance or deviations were identified.
b.
The inspectors noted that some of the items from IE Bulletin No. 79-19 had not been accomplished and would be reviewed for timely completion during a future inspection. (Paragraph 15)
c.
The inspectors expressed concern with the time it takes to repair portable survey instruments. The licensee acknowledp2d the comments. This matter will be reviewed during a future inspection.
(Paragraph 8)
d.
The licensee representative stated the narrative and attach-ment C in the Radiation Safety Manual will be revised to reflect the use of respirator hoods. (Paragraphs 7 and 9 b.)
e.
The inspectors reviewed with the licensee the status of the Area Radiation monitors. (Partgraph 8)
f.
It was noted that the noncompliance item from a previous inspec-tion was closed. (Paragraph 3)
- 13 -
1756 267