IR 05000155/1981007
| ML20009A985 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 06/26/1981 |
| From: | Boyd D, Parker M, Wright G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20009A980 | List: |
| References | |
| 50-155-81-07, 50-155-81-7, NUDOCS 8107140580 | |
| Download: ML20009A985 (4) | |
Text
l
.
.
.
'
U.S. NUCLEAR REGULATORY COMMISSION
'
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No.. 50-155/81-07 Docket No. 50-155 License No. DPR-6 Licensee: Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Facility Name:
Big Rock Point Nuclear Plant l
Inspection At: Charlevoix, MI Inspection Conducted: May 9 - June 12, 1981 Inspectors:
G. C. Wright 6-25-~B/
$
.
M. E. Parker 6 "20'@
bN ~M Approved B D. C.
Projects Section IA Inspection Summary-Inspection on May 9 - June 12, 1981 (Report No. 50-155/81-07)
,
Areas Inspected:
Routine Safety, resident inspector inspection involving:
l Operational Safety Verification, Surveillance Observation, Maintenance,
!
Independent Inspection, NUREG-0737 review and resident inspector seminar.
The inspection involved a total of 151 inspector-hours onsite by two NRC inspectors including 29 inspector-hours onsite during offshifts.
,
l Results: No apparent items of noncompliance were identified, l
l
!
!
t 8107140500 010629 l
PDR ADOCK 05000155 G
,
.
.
.
I DETAILS 1.
Persons Contacted
- C. J. Hartman, Plant Superintendent
- R. E. Schrader, Technical Superintendent
- A. C. Sevener, Operations Supervisor
- E. Raciborski, Quality Assurance Supervisor R. L. Burdette, Senior C&RP Technician J. J. Popa, Maintenance Engineer The inspectors also contacted other licensee personnel including:
Shift Supervisors, Control Room Operators and C&RP Technicians.
- Denotes those present at the exit interview.
2.
Operational Safety Verification The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the month of May. The inspector verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of affected components. Tours of the reactor buildings and turbine buildings were conducted to observe plant equipment conditions, including potential fire hazards, fluid leaks, and excessive vibrations and to verify that maintenance requests had been initiated for equipment in need of maintenance.
The inspector by observation verified that the physical security plan was being implemented in accordance with the station security plan.
The inspector observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection controls. During l
l the month of May, the inspector walked down the accessible portions of the Reactor Depressurization, Core and Containment Spray systems to verify operability. The inspector also witnessed portions of the radioactive waste system controls associated with radwaste shipments.
These reviews and observations were conducted to verify that facility l
operations were in conformance with the requirements established under Technical Specifications, 10 CFR, and administrative procedures.
!
l No apparent items of noncompliance were identified.
3.
Monthly Maintenance Observation Station maintenance activities of safety-related systems and components listed below were observed / reviewed to ascertain that they were con-ducted in accordance with approved procedures, regulatory guides and industry codes or standards and in conformance with Technical Speci-fications.
l l
l
.
!
-2-
?
.
.
.
The following items were considered during this review; the limiting conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; activities were accomplished by qualified personnel; parts and materials used were properly certified; radiological controls were implemented; and, fire pre-vention controls were implemented.
The following maintenance activities were observed / reviewed:
Reactor Depressurization Valve Repair Emergency Diesel Generator Maintenance No apparent items of noncompliance were identified.
4.
Monthly Surveillance Observation The inspector observed Technical Specifications required surveillance testing on the Reactor Depressurization System, Incore Neutron Monitoring System and Emergency Diesel Generator and verified that testing was per-formed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting conditions for operation were met, that removal and restoration of the affected components were accomplished, that test results conformed with Technical Specifications and procedure requirements and were reviewed by personnel other than the individual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personnel.
No apparent items of noncompliance were identified.
5.
NUREG-0737 The inspector reviewed the following NUREG-0737 items and prepared draft safety evaluations for each item, a.
TAP #I.A.I.3.(1)
Shift Manning Overtime Limits b.
TAP #I.C.S.
Feedback of Operating Experience c.
TAP #I.C.6.
Verify Correct Performance of Operating Activities d.
TAP #II.K.3(22a)
RCIC Suction-Verify Procedures.
Not Applicable to Big Rock Point 6.
Independent Inspection Effort The inspectors reviewed the circumstances surrounding the problem encountered during filling of the Reactor Cleanup System on May 5,
-3-
_ _ _ _ _
,
..
o e
1981. While attempting to fill the reactor cleanup system, following cleanup pump replacement, water was observed spraying from a 3/4" pressure test connection.
The water was coming directly from one reactor recirculation loop with the reactor of approximately 1325 psig.
The filling operation was suspended immediately and a pipe cap was placed on the test connection. The cap had been removed during the draining phase of the pump replacement activity and had not been replaced prior to filling.
The inspector reviewed the " Switching and Tagging Order" and SOP-3
" Reactor Cleanup System" and determined that the pipe cap replacement had inadvertantly been left off the " Tagging Order."
The primary system water, which sprayed out of the test connection, was confined to the cleanup pump room and was routed to the radwaste facility via a floor drain. Air samples taken prior to the maintenance activity were between 5.31 and 9.16 E-10 uci/cc (one hour decay time between sample and count).
An air sample taken after the incident indicated an airborn level of 4.88 E-10 uci/cc (10 minute decay time between sample and count).
No offsite releases occurred and there was no persennel contamination.
The licensee is reviewing SOP-3 and will revise the procedure to prevent recurrence of the incident.
The inspector's reviewed Regulatory Guide 1.33, Appendix A and 10 CFR 50 Appendix B Criteria V with the licensee.
No apparent items of noncompliance were identified.
7.
Resident Inspector Seminar Both inspectors attended the resident inspector seminar conducted in Region III during the week of May 11, 1981.
8.
Exit Interview The inspectors met with the individuals denoted in paragraph 1 at the conclusion of the inspection and summarized the scope and findings of the inspection.
-4-i