IR 05000282/1982003
| ML20041F274 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island, Waterford  |
| Issue date: | 02/22/1982 |
| From: | Greger L, Hueter L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20041F268 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.2, TASK-2.B.3, TASK-2.F.1, TASK-TM 50-282-82-03, 50-282-82-3, 50-306-82-03, 50-306-82-3, 80-282-82-3, NUDOCS 8203160352 | |
| Download: ML20041F274 (8) | |
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e U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Reports No. 50-282/82-03(DETP); 50-306/82-03(DETP)
Docket Nos. 50-282; 50-306 Licenses No. DPR-42; DPR-60
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Licensee: Northern States Power Company 414 Nicollet Mall Minneapolis, MN 55401 Facility Name: Prairie Island Nuclear Generating Station, Units 1 and 2 Inspection At: Prairie Island Site, Red Wing, MN Inspection Conducted: January 19-22, 1982 c h. ' h W
Inspector:
L. J. Hueter
.2/2 2/g3 h, f. fy' $b'vffW Approved By:
L. R. Greger, Chief J / M /5'A Facilities Radiation Protection Section Inspection Summary:
Inspection on January 19-22, 1982 (Reports No. 50-282/82-03(DETP);
50-306/82-03(DETP)
Areas Inspected: Routine, unannounced inspection of actions taken in response to post-TMI requirements, two previous items of noncompliance, a previous unresolved item, and other open inspection items. The inspection involved 26 inspector-hours onsite by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
8203160332 820225 ~
PDR ADOCK 05000382 O
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DETAILS 1.
Persons Contacted A. Johnson, Radiation Protection Supervisor J. Oelkers, Quality Control Specialist
- F. Tierney, Jr., Plant Manager
- D. Schuelke, Superintendent, Radiation Protection J. Sorenson, Assistant Production Engineer D. Stember, Associate Production Engineer B. Burgess, NRC Resident Inspector
- Denotes those contacted by telephone on February 12, 1982, for the exit interview.
2.
General This inspection, which began about 12:30 p.m. on January 19, 1982, was conducted to review the status of licensee actions regarding post-TMI requiremen'ts and open inspection items. A tour of various areas of the auxiliary building was conducted.
3.
Licensen Action on Previous Inspection Findings During a previous inspection, certain unresolved matters concerning a radwaste shipment are described. As noted in that report, the matter had been referred to IE:HQ for resolution.
By letter dated May 20, 1981, the Director, IE, notified the licensee of two viola-tions of DOT regulations. The violations involved radiation levels exceeding 200 mR/hr on the external surface of an exclusive use closed transport vehicle, and two drums not having the required
" Radioactive LSA" marking.
In a letter of response dated June 10, 1981, the licensee listed corrective actions taken to preclude The licensee's corrective actions were verified during recurrence.
this inspection and no further problems were identified.
(Closed 282/81-03-01; 306/81-03-01)
4.
Onsite Burial of Nonradioactive Spent Rosin 1 8 As described in previous inspection reports the licensee has a permit from the Minnesota Pollution Control Agency for onsite burial of certain spent resins with little or no potential for radioactive material contamination. The criteria for ascertaining the radioactive status of resins was previously described. Three
IE Inspection Report No. 50-282/78-05; 50-306/78-07
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IE Inspection Report No. 50-282/81-03; 50-306/81-03
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burials of spent resins have. occurred since the 16at report, the latest in May 1981. TWo of these burials involved spent resins from the water treatment plant which provides make-up water for the plant.
Since well water is the source of make-up water (not recycled plant water), these spent resins are exempted from radioactivity monitoring.
The third burial involved secondary system spent resin subject to analysis for potential radioactivity. Analysis performed showed no detectable radioactivity. Continued occasional use of the onsite burial facility, as provided for by procedures and under the terms of the permit, is anticipated.
(Closed 282/78-05-02; 306/78-07-02)
5.
Concerns in SAC Audit Report No. P-79-1 During a previous inspection, it was noted that the Safety Audit Committee in their Audit Report No. P-79-1, dated December 12, 1979, identified concerns in the radiation protection are. involving source inventory accuracy and timeliness, and the need to revise the Chemistry Counting Manual. To improve these areas, the licensee has since reviewed and revised the source inventory system and the Chemis-try Counting Manual. No problems were noted.
(Closed 282/80-02-01; 306/80-02-01)
6.
QA/QC Program for Radioactive Material Handling and Shipping Activities During a previous inspection *, it was noted that the licensee was hiring personnel to set up and implement a quality assurance and control program, and that one area to be covered was radioactive material handling and shipping activities. During a later inspection",
it was noted that a senior health physics technician was transferred to the QC Department and given responsibility for developing a quality control program for inspection of radwaste shipments. During this inspection, it was observed that the licensee has developed and imple-mented quality control inspection procedures for radioactve waste shipments and many other radiation protection and radiochemistry activities. The inspector reviewed selected QC inspection check lists for radioactive waste shipments. No problems were identified.
In addition to this activity, an annual QA audit of radioactive material shipment paperwork is conducted. A selective review of paper work for waste shipments identified no problems.
(Closed
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282/80-02-03; 306/80-02-03)
7.
Attendance at Annual General Employee Training (GET)
During a previous inspection, it was noted that a few plant personnel had not attended annual retraining even though special memos had been issued by the Training Supervisor. The licensee has effectively resolved the problem by pulling the security badge of individuals
IE Inspection Report No. 50-282/80-02; 50-306/80-02
IE Inspection Report No. 50-282/81-03; 50-306/81-03
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(thereby denying them entry to the plant) who fail to comply with retraining requirements. GET retraining is now included in the expanded training provide to all plant groups throughout the year.
(Closed 282/80-02-04; 306/80-02-04)
8.
Status of NUREG-0737 Items Preliminary / final status was determined for the following NUREG-0737 items (long-term) scheduled for implementation by January 1, 1982.
In a letter dated December 30, 1980, from Mayer to Director of NRR, the licensee summarized their understanding of NUREG-0737 requirements and provided a commitment to meet each requirement by a specified date (generally by January 1, 1982) contingent upon equipment avail-ability and absence of unforeseen problems.
In a followup letter dated December 31, 1981, the licensee informed the Commission of delays in implementation of several of the NUREG-0737 requirements, provided a reason for the delay, and a revised implementation schedule (March 1, 1982, for requirements considered in this report),
a.
Plant Shielding (Task II.B.2.2.B, Vital Area Acenss Only)
As summarized in the December 30, 1980 letter, the licensee conducted a design review of plant shiciding for adequacy of maintaining personal exposures within acceptable limits for individuals requiring continuous or periodic access to vital equipment to control and shut down the plant following a post-ulated accident. Using a source term, apparently conservative compared to NUREG-0737 criteria, the review identified several areas needing modification. Feasibility dictated utilization of various types of modifications such as rerouting of piping, and installation of shielding in the form of concrete, lead sandwiched in steel, and bagged sand. The following modifica-tions were made to reduce radiation levels in the auxiliary-building.
(1) Reroute RHR Sump from Waste Hold-up Tank to Containment via the Annulus Sump.
(2) Reroute Sampling System drains to RHR Sump.
(3) Shield the Safety Injection (SI) pump area with approxi-mately 16 inches of concrete.
(4) Install shield curtains in the area of the SI pumps to reduce direct and indirect radiation.
(5) Shield opening from Containment Spray pump room (bags of sand).
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(6) Redesign WHR pit covers so they may be left in place except during maintenance and inspection activities in the pits.
(7) Reroute reactor vessel Safety Injection line.
(8) Reroute Safety Injection line for cold leg injection.
(9) Install additional shielding on floor of 715' level above the RHR lines.
(10) Install miscellaneous shielding in the sample room.
(11) Install additional shielding for the RHR supply to the SI pumps.
(12) Shield the opening where RHR lines enter the CS pump room.
(13) Install additional shielding for stairway enclosures on the 715' level.
(14) Shield the Safeguard MCC's on the 755' level from the Shield Building Vent System filters and from the Auxiliary Building Special Vent System filters.
The licensee stated that all of the above modifications were completed by January 1, 1982.
Installation of 13 of the above modifications were verified by observation.
While " shield modifications" are complete, some may not be ade-quate under certain accident conditions for Unit 2 until a reactor coolant vents system modification is completed. The NUREG-0737 required completion date for equipment which must meet safety-related electrical equipment qualifications is June 30, 1982.
The modified vent system has electrically operated valves which must meet the qualifications. The licensee has requested (letter dated December 31, 1981) an extension for completion date to the next Unit 2 refueling outage, presently scheduled for August 1982. The Unit i vent system modification was said to be complete but,was not verified by the inspector.
Inspec-tion of equipment qualification is assigned to other regional inspectors.
It appears the licensee has met the intent of long-term NUREG-0737 item II.B.2.2.B.
b.
Post-Accident Sampling Capability (Task II.B.3.2.B)
The licensee considers the post-accident sampling and analysis system operational. Some further modifications are being made
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to improve the capability of the sampling system under a wider range of containment atmosphere conditions. The licensee plans to complete these modifications by March 1, 1982.
Although the shielded sampling systems were partially observed during a tour, review of this task item was not completed during this inspection trip.
This item remains open and w'ill be reviewed during a future inspection.
c.
Extended Range Noble Gas Effluent Monitor (Task II.F.1.1.B.2)
The licensee has installed high range noble gas effluent monitors for the main steam lines (two for each reactor) and the shield building vent (one for each reactor).
To aid in evaluating potential noble gas releases from the power operated relief valves and/or the safety valves (upstream of the main steam isolation valves), a section of each of the four main steam lines is " viewed" through a co111 mated lead shield by a Victoreen G-M 'ype exposure rate meter. Curves have been gener-t ated to relate exposure rate to concentration of noble gas in the steam. These curves compensated for changing isotopic ratio with length of time since shutdown and shielding by the steam line, guard pipe, and insulation. The noble gas release rate is obtained by multiplying the concentration times the discharge flow rate as determined from valve position indicators and flow devices. The above parameters are fed directly into a computer which is programmed to provide a release rate.
The 100 R/hr range of the meters is adequate. The curves that relate exposure rate to concentration of noble gas show that about 30 R/hr corresponds to the NUREG-0737 specified design basis concentration of IE3 uCi/cc xenon-133 equivalent.
In a letter to NRR dated December 31, 1981, the licensee related their inability to meet the January 1, 1982, implementation commitment for the steam line monitors due to a faulty electrical component and consequent uncompleted electrical equipment check-i
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out and calibration.
In the letter, the licensee requested an extension of the implementation date to March 1, 1982.
i To monitor noble gas releases from other areas of the plant during i
accident conditions, an off-line noble gas monitoring system has been installed on the shield building vent of each reactor unit.
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If accident conditions occur, any purging operation, either con-tainment or inservice purge, would be terminated. Further, the
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auxiliary building normal exhaust (which also includes the steam
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jet air ejector exhaust) is isolated and diverted to become one
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of three inputs to the shield building exhaust. Radwaste build-ing ventilation and. spent fuel pool normal ventilation will also
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be isolated following an emergency. These three inputs, each
of which passes through a PAC filter unit (pre-filter, absolute
particulate filter, and a charcoal filter) are the auxiliary
- building special, the shield building special, and the spent fuel pool special.
A sampler, designed to collect an isokenetic sample of the
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filtered exhaust air in the shield building vent, directs the
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sample through a flow spliter. The high flow rate path.is
designed for low activity samples while the low flow rate path'
is designed for high activity samples. Each flow path is directed
- through a particulate filter and a silver zeolite filter followed by a noble gas monitor before being routed back to the vent.
The previously existing gas monitor is used for the low activity l
pathway. A Victoreen Model 845 fon chamber has been installed for the high activity pathway. This monitor has a range of 0.1 to
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j 10 mR/hr. The monitor'has adequate range to measure a concen-
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tration of 10' uC1/cc of xenon-133 equivalent, the criteria specified in NUREG-0737 for diluted exhaust gases. Using a
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i nominal 20 C1 Cs-137 solid source, satisfactory calibration I
and linearity have been demonstrated up to 10" mR/hr. Higher f
range calibration is planned when a 260 C1 Cs-137 source (on order) is obtained. Calibration curves have been developed which relate monitor readings to Xe-133 concentration.
It appears the licensee has met the intent of the long-ters
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NUREG-0737 Item concerning extended range noble gas monitoring
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for the shield building vent pathways, but not for the main steam line pathways. This item remains open and will be re-
viewed during a future inspection.
I d.
High Level Iodine and Particulate Effluent Sampling and Analysis (Task II.F.1.2.B.2)
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The high level iodine and particulate effluent sampling system
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is described in paragraph c. above. The design of installed
equipment appears to provide a representative sample. Although an evaluation does not indicate the necessity of a heat traced
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sample line, it is being provided as a precaution. Using the l
NUREG-0737 specified criteria, the licensee has designed and l
built a shielded sample collection system. This system will j
permit sample removal and placement in a shielded pig while
limiting exposure to the whole body and the extremities to a
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small fraction of the respective exposure rates specified in the criteria.
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Procedures for sample collection, handling, and analysis are
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provided.
If the. regular onsite laboratory facility becomes unavailable, the mobile laboratory, which has a routinely r
calibrated GeLi system, may be used.
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It appears the licensee has met the intent of the long-term NUREG-0737 item for high level lodine and particulate sampling and analysis.
e.
Containment High-Range Radiation Monitor (Task II.F.1.3)
The licensee has installed two General Atomic high range monitors in each containment, physically separated to view major portions of each containment. Delivery of environmentally qualified cable has been a problem. By letter dated December 31, 1981, the 11-censee notified the Commission of their inability to meet the implementation commitment of January 1, 1982, for the containment high-range radiation monitor.
In the letter, the licensee re-quested an extension of the impicmentation date to March 1, 1982.
Therefore, this item was not reviewed in detail and is an open item that will be reviewed during a future inspection.
Exit Meeting The inspector contacted licensee representatives (denoted in Section 1)
by telephone on February 12, 1982. The following items were discussed:
a.
The purpose and scope of the inspection.
b.
Previous items of noncompliance and open items.
c.
The inspector identified the long-term NUREG-0737 items due for completion on January 1, 1982.
Installation and implementation of items completed were inspected (except the Post Accident Sampling System) with no problems being identified. The inspector acknow-ledged the licensee's submittal of a request for an extension to March 1, 1982, for noncompleted systems. The licensee stated that he anticipates meeting the March 1 completion date.
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