IR 05000280/1982014
| ML20058C336 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/28/1982 |
| From: | Barr K, Hosey C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20058C330 | List: |
| References | |
| 50-280-82-14, 50-281-82-14, IEB-80-03, IEB-80-3, NUDOCS 8207260319 | |
| Download: ML20058C336 (8) | |
Text
. - _
_ _ _ _
_ _ _ _ _.. _ _ _ _ _.-
-
._.
. _.
_ _ _ _ _ _ _ _ _.
-
_
_
'
'
p erTo
'o UNITED STATES
NUCLEAR REGULATORY COMMISSION
n
REGION II
g
< *r o
101 MARlETTA ST., N.W., SUITE 3100 j
o ATLANTA, GEORGIA 30303
.....
JUN 2 91982 Report Nos. 50-280/82-14 and 50-281/82-14 i
'
Licensee:
Virginia Electric and Power Company
}.
Richmond, VA 23261 Facility Name:
Surry 1 and 2 Docket Nos. 50-280 and 50-281 License Nos. DPR-32 and DPR-37 i
Inspection at Surry s te near Surry, VA b !3-3!d'k Inspector:
/q
. h C. M J Ho sek \\
Date Signed
,
,,ctop S
82-Approved by:_.K. P. Barr, 5@ ion Chief Date ' Signed Technical Inspection Branch
Division of Engineering and Technical Programs SUMMARY
!
Inspection on Jene 1-4, 1982 Areas Inspected This routine, unannounced inspection involved 35 inspector-hoers on site in the r
l areas of radiation protection program, followup on IE Circulars and Bulletins,
'
followup on previous enforcement matters and unresolved items, followup on previous inspector identified items, and followup on licensee event reports.
Results In the areas inspected, no violations or deviations were identified.
l
,
8207260319 820629 PDR ADOCK 05000280 G
,. ~ _...
.
.
,
._ -,, _
.-
.
.
.
- - - -.
-
- - - - -.. - -
. -
-
.
.
REPORT DETAILS 1.
Persons Contacted Licensee Employees
- R. F. Saunders, Assistant Station Manager
- S.
P. Sarver, Health Physics Supervisor E. S. Grecheck Design Control Supervisor
- 0. J. Costello, Staff Assistant P. Nottingham, Assistant Health Physics Supervisor M. Beckham, Assistant Health Physics Supervisor D. Der.smore, Assistant Health Physics Supervisor T. Kendria, Engineer
- H. F. Kahnhauser, Health Physicist (Corporate)
Other licensee employees contacted included four technicians, three operators, two mechanics, two security force members, and two office personnel.
NRC Resident Inspector
- D. J. Burke, Senior Resident Inspector
- M. Davis, Resident Inspector
- Attended exit interview 2.
Exit ?nterview The inspection scope and findings were summarized on June 4, 1982, with those persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings a.
(Closed) Infraction (280/79-09-05) Trash Rack for Containment Spray System Not in Place.
The inspector reviewed changes made to OP-1B, Containment Checklist, and verified that the checklist includes an inspection of the sump screens and grating.
The inspector had no
further cuestions.
b.
(Closed) Violatien (280/81-25-01) Failure to Follow Procedures.
The inspector reviewed the corrective action specified by the licensee and had no further questions.
c.
(Closed) Violation (280,281/81-25-02) Failure to Post High Radiation Area.
The inspector reviewed the corrective action specified by the licensee. During tours of the plant the inspector observed no further violations of posting requirements.
.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
.
d.
(Closed) Violation (280,281/81-30-01) Failure to Post Radiation Area.
The inspector reviewed the licensee's corrective action and had no further questions.
During tours of the plant the inspector observed no f urther violations of posting requirements.
e.
(Closed) Unresolved Item (280,281/81-30-02) The inspector reviewed the protective clothing and air sampling requirements for sorting radioactive waste in the old drumming station on the 27 foot elevation of the auxiliary building. Continuous air sampling is required in the area while opening bags of waste.
The radiation work permit also required a full-face respirator be worn while opening bags of waste.
No violations or deviations were identified.
The licensee is in the process of upgrading the auxiliary building ventilation system and the flow of air f rom potentially contaminated to clean areas should be addressed during the plant modifications.
4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or devia-tions. New unresolved items identified during this inspection are discussed in paragraph 7.
5.
Followup On IE Bulletins and Circulars a.
Circular 79-21, Prevention of Unplanned Releases of Radioactivity.
During a recent review of actions on IE Bulletins and Circulars, the licensee found that IE Circular 79-21 had not been evaluated by the plant.
A plant review completed in May 1982, indicated several plant modifications could be made to prevent unplanned releases.
These include construction of dikes to prevent water from running under doors to the outside and plugging the vents on the Refueling Water Storage Tank (RWST) and permit the tanks to vent through an overflow line to valve pits where the vented gases could be picked up by a monitored ventilation system.
This item will remain open pending completion of actions by the licensee (280/82-14-01).
b.
Bulletin 80-03, Loss of Charcoal From the Standard Type II, 2 Inch Tray Adscrber Cells. The licensee has the Type II adsorbers. However, defects in the trays which could result in the loss of charcoal have not been identified curing routine surveillances.
c.
Circular 80-14 Radiation Contamination of Plant Demineralized Water System and Resultant Interna; Contamination of Personrel. The licensee uses temporary jumpers to connect the demineralized water system to radioactive systems. The use of jumpers is documented ar.d controlled.
In addition. backflow preventors have been installed and are periodi-cally tested.
Instructions nave been issued that pronibit the use of demineralized water for human consumption.
_
_ _ _
_
-..
_
._ _ _ _-. _____
_ _ _ _
.
.
6.
Followup' on Previous Inspector Identified Items (IFI)
a.
(Closed) IFI (280,281/78-08-03) Correlation Study of Liquid Monitor.
The licensee is in the process of installing a new Radioactive Liquid Monitor, RM-LW-108, in a low background area en the 15 foot elevation of the auxiliary building.
The new monitor is a clamp-on scintil-lation type monitor. The system is wesigned for easy decontamination.
Design Change 81-12 for this installation was approved by the Station Nuclear Operations Safety Committee on March 19, 1981. The inspector stated that the installation, calibration, and operation of this monitor will be reviewed in a subsequent inspection (280/82-14-02).
b.
(Closed) IFI (280/78-27-05) Ventilation Vent Flow Indication and Readout.
The licensee has installed new flow measuring and readout devices in the control room for the Ventilation Vent as a part of the plant ventilation upgrade.
The normal flow rate now falls near mid-scale of the flow indicating meter. The inspector had no'further questions.
c.
(Closed) IFI (280/80-29-07; 281/80-33-07) Evaluation of Neutron
-
Monitoring Device.
The licensee performed a test of the neutron monitoring device in use at the time of the HP appraisal and determined that the device would not satisfactorily measure neutron doses less than 100 mrem. The licensee discontinued using the device and now uses stay time and neutron instrument readings to determine personnel neutron doses.
d.
(Closed) IFI (280/80-29-09; 281/80-33-09) Computerization of Dosimetry Records. The licensee has completed the transfer of dosimetry records to a computer system and is now operating the computer system in parallel with the manual system to identify any errors in the computer program.
The licensee estimates that by the end of 1982, they will eliminate the manual record system.
i
'
e.
(Closed) IFI (280/80-29-13; 281/80-33-13) Quantitative Fit-Testing and Annual Refit for Respirators. The licensee has acquired a quantitative fit-test booth and is now performing quantitative fits for respirator users.
Procedures have been revised requiring an annual refit for respirator users.
,'
f.
(Closed) IFI (280/80-29-17; 281/80-33-17) Documentation of Whole Body Spectrum.
The licensee is now principally using a chair type body counter which includes a computer-baseo multichannel analyzer.
The system performs isotopic identification and provides a.hard copy cf the spectrum as well as the basic analysis results.
~
g.
(Closed) IFI (280/80-29-19; 281/80-33-19) Need for Tent During S/G Plugging Operations. The licensee has discontinued using a tent around the manways on the steam generators during eddy current inspection and will not use one if they have to plug tubes.
The steam generator cubicle is considered the controlled area for generator work.
1
)
-
_ - _ _ _ _ _ _ _ _ _ _ _ _ _ _
.
.
h.
(0 pen) IFI (280/80-29-20; 281/80-33-20) Establishment of a Formal ALARA Program for the Plant.
The licensee has prepared a formal ALARA program for the plant. However, it has not been approved by the plant management. This item will remain open pending approval of the program by plant management and a review of the approved program by the inspector.
i.
(Spen) IFI (280/80-29-24: 281/80-33-24) Balancing of Auxiliary Building Ventilation Flow. This item will remain open pending completion of the auxiliary building ventilation system modifications and a review of the air flow by the inspector.
j.
(0 pen) IFI (280/80-29-27; 281/80-33-27) Consideration of Method to Collect Ground Water. The licensee is in the process of implementing Design Change 81-51 which will eliminate the inflow of ground water from the auxiliary building piping tunnel sump to the auxiliary building basement. Presently, the leak rate of ground water into the sump is approximately 10 gallons per minute.
The leak path was designed in the sump to reduce the ground water level in the area.
Water in the sump will be pumped to the. Unit 1 Drain Tunnel which is monitored.
Pumping will be secured if fl_ coding of the auxiliary building basement occurs until the radioactivity concentration is determined.
In addition, a 3-6 inch wall will be constructed around
,
the sump to prevent the intrusion of potentially contaminated water from the auxiliary building basement. Sample-lines will be installed so that health physics personnel can sample the sump on a daily basis.
Fl~ w from the sump will be recorded.
This item will remain open o
pending completion of the design change and a review of the installa-tion by the inspector.
k.
(Closed) IFI (280/80-29-29; 281/80-33-29) Consiaeration of Background on Radiation Monitor During Releases. See paragraph 6.a.
1.
(Closed) IFI (280/80-29-30; 281/80-33-30) Monitoring of Potential Release Paths. See paragraph 6.j.
m.
(Closed) IFI 280/29-31; 281/80-33-31) New Solid Waste Building. The licensee uses the new low level waste storage building for a staging area for waste which is ready for shipment to a burial facility. The quantity of solid radioactive waste at the station appears to be decreasing.
n.
(Closed) IFI (280/80-29-32; 281/80-33-32) Consideration of New Waste Compacting System. The licensee purchased and is now using a LSA box compactor.
o.
(Closed) IFI (280/89-29-33; 281/80-33-33) Additional Space for Trash Compacting. With the purchas? of the new box compactor, the licensee moved trash compacting operations out of the auxiliary building to a separate building.
The inspector toured the facility and had no further questions.
b
.
.
.-. _ - _. - -
.
. -. - -
-
.-
_
-
.-
- .
-
.
,
p.
(Closed)
IFI (280/80-29-34: 281/80-33-34) Numbering Each Waste Shipment.
The licensee now numbers each waste shipment, as well as l
each individual package to facilitate tracking the shipment.
!
q.
(Closed) IFI (280/80-29-35; 281/80-33-35) Estimation of Transport
!
Groups I and II Materials. The licensee has reviewed this item and has
determined that current practices are adequate. The inspector had no further questions.
r.
(Closed) IFI (280/80-29-36; 281/80-33-36) Checkoff Sheet to Meet Each Shipping Requirement.
The licensee has reviewed this item and has determir ed that the. checkof f list used for radioactive material I
shipments are adequate. The inspector haa no further questions.
,
s.
(Closed) IFI (280/80-29-37; 281/80-33-37) Air Conditioning for i
Calibration Room. The licensee has installed an air conditioner in the calibration room. The inspector toured the facility and had no further
questions.
i t.
(Closed) IFI (280/80-29-38; 281/80-33-38) Surgeon's Caps for Respirator Wearers. The licensee has evaluated this item and has determined that i
the use of surgeon's caps was not necessa ry at this time.
The l
inspector had no further questions.
u.
(Closed) IFI (280/80-29-39; 281/80-33-39) Periodic Calibration of
'
Multi-Source Gamma Calibrator. The licensee has reviewed this item and has determined that the calibrator is traceable to a primary standard.
Therefore, checking the calibrator with certified instruments is not i
necessary unless the calibrator malfunctions. The inspector had no further questions.
l v.
(Closed)
IFI (280,281/81-30-03) Inspection and Testing of Air j
Regulators.
The licensee has acquired a testing panel for air regulators used in the respiratory protection program.
The licensee
'
now periodically tests air regulators.
The inspector had no further questions.
i w.
(Closed) IFI (280.281/81-30-04) Supplied Air Manifold Filter Change.
The licensee has established a program to change the filters in the l
supplied air manifolds after each use and to periodically test the air
!
flow regulators in the manifolds.
Tne inspector had no further
'
questions.
I
{
7.
Licensee Event Reports l
LER 81-074/03L-0, Uncontrolled Release.
This LER reported an event in
,
which leaks from stripper feed steam heater,1-BR-E-10A, drained into the
auxiliary steam drain receiver, where pumps taking suction, discharged j
contaminarts into the makeup water header.
Comtaminants from the header tnen fillel the unit 2 safeguards heating system drain receiver. The i
,
i iL
__ _ _ _. _.
.
..
_. - _
_
.
heating system drain receiver overflowed, via a vent, into the storm drain system.
The inspector reviewed corrective actions taken by the licensee.
The auxiliary steam drain header is sampled on a daily basis. The licensee has initiated an engineering study to investigate contaminated leakage into tne auxiliary steam drain header. This investigation is still in progress.
The inspector stated that he would review the results of the engineering study during a subsequent inspection (280,281/82-14-03).
8.
Posting, Labeling and Control The inspector reviewed the licensee's posting and control of radiation areas, high radiation areas, airborne radioactivity areas, contamination areas, and radioactive material areas, and the labeling of radioactive material during tours of the plant.
Technical Specification 6.4.B.1.a requires that the entrance to a high radiation area in which the intensity of radiation is equal to or greater han 1000 mrem /hr be provided with locked barricades to prevent unauthorized entry into these areas.
During a review of radiological deficiency reports, the inspector noted that on November 8,1981, a member of the health physics staff found a gate (gate No.15,13' elevation of auxiliary building) to a high radiation area open and unattended.
It appears that after identification of a violation of Technical Specifications, no corrective action was initiated. A licensee representative stated that he was unsure why no action was taken, but perhaps the area was not required to be locked, or corrective action was taken and not properly documented. The inspector stated that this item will remain unresolved pending completion of an investigation by the licensee (280,281/82-14-04).
Failure to keep the entrance to each high radiation area in which the intensity of radiation is equal to or greater than 1000 mrem /hr locked to prevent unauthorized entry would be a violation of Technical Specification 6.4.B.1.a.
During tours of the plant, the inspector observed that large areas of the auxiliary building were roped off and posted as contamination areas. There appeared to be a significant increase in the number of areas since previous inspections.
The inspector discussed with a licensee representative the increased potential for personnel contamination incidents as the plant increases the number of areas requiring protective clothing. A licensee reprsentative stated that there has been no significant increase in the number of personnel contaminations at the plant.
The inspector stated that licensee should consider establishing an aggressive leak-repair and area decontamination program to reduce the number of posted radiological areas in the plant.
During tours of the plant, the inspector ooserved that housekeeping in the waste sorting area in the auxiliary building (old trash drumming station) is in need of improvement. Used drums were piled in part of the area and bags of radioactive waste were piled four or five bags high. Very little working area was available in the room. A licensee representative stated that they
.
..
were working to reduce the quantity of material stored in the room, The drums are to be transferred to the waste - ompacting building and compacted.
Tne room is used to sort compressible from noncompressible waste and wet from dry waste. The radiation work permit for the room requires the worker to wear a full-face respirator when opening bags and for the airborne radioactivity levels to be continuously sampled. The inspector stated that the licensee should consider separating the storage area from the sorting area to minimize the exposure to personnel sorting the material from stored radioactive material.
The licensee representative acknowledged the inspector's comments.
9.
Posting of Notices 10 CFR 19.11 requires, in part, that each licensee post current copies of 10 CFR 19 and 10 CFR 20 or if posting of the documents is not pract;:?ble, the licensee may post a notice which describes the document and states w.
+a it may be examined. 10 CFR 19.11 further requires that copies of any Notice of Violation involving radiological working conditions be conspicuously posted within two working days after receipt of the documents from the Commission.
The inspector observed the posting of notices required by 10 CFR 19.11 and had no questions.
10.
Surveys The inspector performed independent radiation and loose surface contamina-tion surveys in the auxiliary building and in the restricted areas outside and verified that the areas checked were properly posted.
11.
Notification and Reports The inspector reviewed the licensee's records to determine if exposure data had been provided to terminated employees as required by 10 CFR 19.13(d).
The inspector selected several names of recently terminated employees and l
verified that each employee had been sent a letter regarding his exposure
,
history. The inspector had no further questions.
12.
External Exposure Control During tours of the plant, the inspector observed workers wearing personnel monitoring devices (pocket dosimeter and/or TLD). The inspector discussed the dose monitoring program with licensee representatives.
The inspector also reviewed computer printouts for several plant departments and verifiec that the radiation dose recorded for 1982 appeared to be well within NRC limits.
The licensee was maintaining the records of radiation exposure required by 10 CFR 20.401. No violations or deviations were identified.
.