IR 05000387/1991014
| ML17157A847 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/05/1991 |
| From: | Noggle J, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17157A846 | List: |
| References | |
| 50-387-91-14, 50-388-91-14, NUDOCS 9109170160 | |
| Download: ML17157A847 (4) | |
Text
Docket Nos.
License Nos.
V. S. NUCLEAR REGULATORYCOMMISSION
REGION I
50-387 50-388 NPF-14 NPF-22 Licensee:
Penns lvania Power and Li ht Com an 2 North Ninth Street Allentown Penns lvania 18101 Facility Name:
Inspection At:
Sus uehanna Steam Electric Station Units 1 4 2 Berwick Pennsylvania Inspection Conducted:
Au ust 20-21 1991 Inspector; Approved by:
J.
o gle, iation Specialist Facthties Radiation Protection Section W. Pasciak, Chief, Facilities Radiation Protection Section date 5- ~ 'li date Ins ection Summa: A radwaste/transportation regional initiative inspection was conducted on August 20-21, 1991.
AAPAA:Ad~ iiip iidd':p iy identified items, Nuclear Quality Assurance surveillance reports, and the review of two (2) irradiated reactor hardware radwaste shipments.
Results:
Within the scope of the inspection, no violations were identified.
P
~ >0~ hO 9 1 0905 PDR ADOCK 05000382 PDR
DETAILS 1.0 Personnel Contacted 1.1 Licensee Personnel
"J. Collins, Health Physics Technician
- T. Dalpiaz, Manager of Plant Services T. DeBortoli, Nuclear Quality Assurance Surveillance
- D. Hagan, Effluents Management Supervisor J. Long, Refuel Floor Supervisor J. Porta, Chem Nuclear Services, Inc. Supervisor
- D.'Roth, Senior Compliance Engineer R. Scena, Health Physics Technician V. Zukauskas, Assistant Health Physics Foreman 1.2 NRC Personnel
- G. Barber, Senior Resident Inspector
- Denotes those present at the exit interview on August 21, 1991.
Other licensee employees were contacted and interviewed during this inspection.
2.0 P~ur ose Due to the potential radiation safety hazard of handling high activity reactor vessel components, a two (2) day radwaste-transportation regional initiative inspection was conducted to witness the handling and shipping of Type B, Class C radwaste.
3.0 Review of Previousl Identified Items During a previous inspection, the inspector questioned the adequacy of defined QA/QC oversight of the Spent Fuel Pool Cleanout Project.
The inspector reviewed the licensee letter PLIS-37627 dated 6/27/91, which summarized further definition of QA/QC involvement in the project.
Several project procedures were revised to include QA notification when upper travel stops of the working crane are changed to ensure a minimum of seven (7) feet of water shielding is maintained at all times.
Also QA notification was included for any instance when the water level in the cask storage pit is lowered.
The inspector also reviewed the
QC surveillance involvement to date (Refer to Section 3.0) and was satisfled that the licensee has adequately focused the necessary attention in this area.
4.0 uali Control Surveillance Re orts The following Quality Control Surveillance Reports were reviewed.
QA Surveillance Report No.91-043 dated 7/30/91 reviewed the dose profiling of or dose measurement of submerged irradiated reactor hardware with derived activity determinations.
The inspection period was 5/20/91 - 6/13/91 and no findings were identified.
QA Surveillance Report No.91-045 dated 8/14/91 reviewed the control rod blade processing and loading into the first radwaste liner. The inspection period was 6/12/91 - 6/26/91 which resulted in one (1) finding of low safety significance regarding current procedure revision in use on the refuel floor.
QA Surveillance Report No.91-047 dated 8/20/91 reviewed the control rod blade processing and loading into liners 2-4. The inspection period was 6/27/91 - 7/11/91 and resulted in one (1) finding where a backshift Refueling Floor Supervisor was not present on the refueling floor as required by procedure.
A maintenance management commitment was obtained as a corrective measure.
The spent fuel pool cleanout project thusfar has not demonstrated any significant safety hazards and appears to have control on quality.
5.D
~Y The inspector witnessed the final survey, final vehicle inspection, and completion of the shipping manifest of a previously loaded and packaged shipment (no.91-137). The inspector reviewed a second Type B shipment (no.91-138) from the initial loading of the shipping cask, decontamination of the shipping cask, and bracing of the cask onto the shipping trailer.
The inspector reviewed the shipping cask (3-55) Certificate of Compliance no.
5805 and verified that all requirements had been met with regard to SSES radwaste shipments no.91-137 and 91-138.
Shipment no.91-137 was calculated by Waste Management Group, Inc. (WMG) to contain 1.73 E 4 curies, Class C wastes.
WMG was audited by the Nuclear Utilities Procurement Issues Council
(NUPIC) by Long Island Lighting Company audit no. SA-19-05 on April 23 - 24, 1991.
This audit encompassed the computer programs RADCOR and RADMAN (which were used by WMG for the above shipment calculations), program'ontrols and documentation.
The NUPIC audit did not result in any findings.
The inspector witnessed the loading of shipment no.91-138.
Several steps were taken in order to minimize contaminating the external surfaces of the shipping cask.
The floor of the flooded Cask Storage Pit (CSP) was vacuumed before lowering the shipping cask into the CSP.
The bottom of the cask was covered in herculite and the cask was thoroughly wetted with deionized water before entering the flooded pit area.
The previously loaded and capped steel liner was placed on the cask base plate, cask top replaced, and reattachment bolts hand tightened before removing the loaded cask from the pool, As the cask was being lifted out of the pit the external cask surfaces were again rinsed with deionized water to wash off contaminants.
After the cask cleared the CSP water line, the liftwas halted to allow drainage of the cask and liner. The cask was only exposed to the CSP enviornment for (3) hours.
The inspector and a licensee QA representative witnessed 22 minutes of drain down time (a minimum of 20 minutes required by procedure).
The inspector later questioned the derivation of the 20 minute value and was satisfied that the licensee had performed calculations supporting this value.
After reaching the refuel floor the cask was surveyed, decontaminated twice, and all applicable bolts were torqued to appropriate values. A final leak test was performed by fillingthe drained cask with four (4) psig of air and verifying no drop of air pressure occurred after 30 minutes.
Finally the impact limiters were fitted to the cask and it was placed on its shipping trailer and secured for transport.
The radiation survey revealed less than 1000 dpm/100cm with a maximum contact dose rate of 160 mR/hr. The above mentioned loading and packaging evolutions were accomplished smoothly and efficiently in less than one (1) day.
No discrepancies relative to NRC or DOT transportation regulations were observed.
6.0 Exit Meetin The inspectors met with licensee representative at the conclusion of this inspection, on August 21, 1991.
The inspector reviewed the purpose and scope of the inspection and reported no inspection findings.