IR 05000302/1978029
| ML19259A901 | |
| Person / Time | |
|---|---|
| Site: | Crystal River |
| Issue date: | 11/30/1978 |
| From: | Dance H, Quirk D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19259A891 | List: |
| References | |
| 50-302-78-29, NUDOCS 7901110176 | |
| Download: ML19259A901 (7) | |
Text
.
.
UNITED STATES
- gght #880g NUCLEAR REGULATORY COMMISSION o,
[
'o REGloN 11
,,,
101 M ARIETT A sTRE ET. N.W.
g
e ATL ANT A. GEORGI A 30303
'$
/
...*
Report No.: 50-302/78-29 Docket No.: 50-302 License No. : DPR-72
.
Licensee: Florida Power Corporation
',
320134th Street South P. O. Box 14042 St. Petersburg, Florida 33733 Facility Name: Crystal River 3 Inspection at: Crystal River Site, Crystal River, Florida Inspection conducted: November 6-9, 1978 Inspector:
D. R. Quick
// 3
'77 Approved by:
. (ww H.
C'. Danc e, CbTe f Date'
'
Reactor Projects Section No. 1 Reactor Operations and Nuclear Support Branch Inspection Summary Inspection on November 6-9, 1978 (Report No. 50-302/78-29)
Areas Inspected:
Routine, unannounced inspection of plant operations; follow-up on previous noncompliance items and unresolved items; follow-up on licensee events, and a plant tour. The inspection involved 31 inspector-bours on-site by one NRC inspector.
Results:
No items of noncompliance were identified in three of the four areas inspected.
One item of noncompliance was identified in one area (Inf raction - Failure to follow procedures (78-29-01 - paragraph I.S.c).
_. -
e
=
7901110/70
.
RII Report No. 50-302/78-29 I-1 il 3
DETAILS I Prepared by: D. 'R. Quick, Reactor Inspettor Datd Reactor Projects Section No.1 Reactor Operations and Nuclear Support Branch Dates of Inspectign: No aber 6-9, 1978-b t i f 30 ")8 Reviewed by:
H. C. Dance, Chief Date'
'
Reactor Projects Section No.1 Reactor Operations and Nuclear Support Branch 1.
Persons Catacted Florida Power Corporation (FPC)
- G. P. Beatty, Jr., Nuclear Plant Manager
- W. R. Nichols, Operations Superintendent
- P. F. McKee, Technical Services Superintendent
- G. M. Williams, Compliance Plant Engineer
- G. R. Westager, Maintenance Superintendent
.K. O. Vogel, Operations Engineer
- J. N. Hessinger, Compliance Auditor
- Denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings None.
3.
Unresolved Items None.
4.
Exit Interview
,
A meeting was held by D. R. Quick with G. P. Beatty, Jr., and seabers of his staf f on November 9,1978. Items covered by this inspection were discussed, including a new noncompliance item concerning the jumper log (see paragraph 5.c). The licensee indicated corrective action would be take *
.
.
RII Report No. 50-302/78-29 I-2 5.
Review of Plant Operation As part of a general review of plant operations, the inspector reviewed the following areas for nonconformance with Technical Specifications and Administrative requirements:
Control Room Operator's Log
-
Shif t Supervisor's Log
',
-
Jumper Log
-
,
a.
Control Room Operator's Log The inspector reviewed this log for the month of October,1978.
No discrepancies were identified for this period.
b.
Shif t Supervisor's Log The inspector reviewed this log for the month of October,1978.
No discrepancies were identified for this period.
c.
Jumper's Log The inspector reviewed this log for the period September-October, 1978. Two discrepancies were identified. Technical Specification 6.8.1 requires that Administrative Procedures, as recommended by Regulatory Guide 1.33, be established, implemented, and maintained.
Compliance Procedure 114 implements the control requirements for temporary modifications (Jumpers). This procedure requires, in part, that :
(1) a jumper record be maintained; (2) the duty Shif t Supervisor review this jumper record to appraise himself of this aspect of plant status; (3) the Shif t Supervisor approve all jumpers prior to installation; and (4) jumper removal be verified and reflected in the jumper record by the Operator on duty.
Contrary to these requirements, control of jumpers was not main-tained in the following two instances:
(1) On September 27, 1978, jumper number 09-94 was installed af ter the jumper record had been disapproved by the Shif t Supervisor. In addition, Surveillance Procedure 443 indicated, by initials, that the duty Shift Supervisors had reviewed the j umper records daily from September 27, 1978, through November 7, 1978. Upon noting the discrepancy on November 8, 1978, the inspector determined, through discussions with licensee personnel, that the jumper in question was valid, was still installed at that time, and that disapproval of the jumper record was an inadvertent error.
The Shift Supervisor on duty November 8,1978, corrected the discrepancy immediately. This jumper was initiated to install a guage to monitor seal pressure on "D" reactor coolant pump due to fluctuations in pressure.
-4
..
,
.
RII Report No. 50-302/78-29 I-3 (2) On September 13, 1978, jumper record number 09-41 was initiated and approved to install a mechanical gag on "B" sain steam line safety valve MSV-39 due to steam leakage through the valve.
The gag was installed on that date. The gag was later removed and the valve repaired during a shutdown which was initiated on September 20, 1978. This jumper, while in place, limited unit power to 85% in acqordance with Technical Specification 3.7.1.1.
On November 8,.1978, with the unit 98% power, the inspector noted that jumper record 09-41 athad not been cleared. Investigation revealed the gag to be laying near the safety va.ve in question,but not installed.
The jumper tag was still attached to the gag. The duty operator immediately rectified the discrepancy by clearing jumper record 09-41.
As previously noted, the duty Shift Supervisors indicated, by initialing Surveillance Procedure 443, that they had reviewed the jumper records daily from September 13, 1978, through November 7,1978.
These two examples constitute a single item of noncompliance (Failure to follow procedures) which is classified as an infraction (78-29-01).
These discrepancies were discussed with the licensee during the exit interview.
The licensee acknowledged the inspector's concerns and stated that corrective action would be taken to prevent recurrence of this type problem.
6.
Review of Outstanding Items List The inspector reviewed all outstanding items with the licensee to verify that ?. hey are all being tracked and that corrective action is being taken. The review included all noncompliance items, unresolved items, open items, and deviations. Some discrepancies were identified but all were resolved. The inspector is satisfied that all items are presently being traeLed and has no further questions at this time.
7.
Review of Aegulatory Guide 1.16 Report.ag Requirements
'
The inspector reviewed these reporting requirements with the licensee in an attempt to clarify the Inspection and Enforcement position on this satter and rectify any misunderstandings which may have existed.
Upon conclusion of the discussion the licensee stated that he understood the IE position and would coeply with the requirements.
8.
Review of Licensee Event Reports The inspector reviewed selected LER's for ccasistency with the require-ments of the Technical Specifications and Regulatory Guide 1.16 (Reporting
.
.'
RII Report No. 50-302/78-29 I-4 of Operating Information - Appendix A Technical Specifications). The inspector examined the licensee's analysis of the eveut, the corrective action taken, and discussed the LER with licensee representatives.
The following LER's were reviewed:
LER 78-003 Unit 2 Battery Inoperable a.
.
This LER is closed without comment.
.
b.
LER 78-017 BPRA Failure and Loose Parts This LER is closed as a result of NRR's evaluation of the event and their subsequent approval for plant restart.
c.
LER 78-019 ECCS Small Break Analysis This LER will remain open pending the inspector's review of all NRR - licensee correspondence on the matter.
d.
LER 78-02) Fire Service Valve Inoperable This LER will remain open pending completion of the licensee's generic review of the Fire Protection System to ascertain whether or not this condensation problem exists in any of the other fire service valve control boxes.
LER 78-024 Reactor Protection System Possible Grounding Proble=
e.
This LER was generated as a result of B&W concern for the possi-bility of a loss of systes ground affecting the protection system in a non-conservative manner.
B&V reported this concern via 10 CFR 21 requirements and made modification recommendations to affected licensees. The recommendation consisted of a method of monitoring the condition of the systen ground while performing normal surveillance testing. This modification was approved and made by the licensee via MAR 78-4-7 and Surveillance Procedure 110 was changed to include ground monitoring. The inspector reviewed the modification package and has no further questions at this time. This LER is closed.
f.
LER 78-027 Quadrant Tilt Limits Change Technical Specification Amendment 16, dated September 1, 1978, revised the quadrant tilt limits to include detector uncertainties based on detector operational characteristics and detector normalt-zation. The licensee subeitted a revised LER which was received by the inspector on October 26, 1978. The inspector reviewed both the amendment and the revised LER with the licensee and has so further questions at this time. This ID is close.
.
.
'
RII Report No. 50-302/78-29 I-5 LER 78-043 Auxiliary Building Exhaust Fans Inoperable g.
This LER is closed without comment.
h.
LER 78-044 Position Indication on CFV-15 Inoperable The inspector reviewed torque and limit switch problems with the licensee during previous inspections. The Licensee is evaluating these problems. This LER is closed.
i.
LER 78-045 Control Complex Ventilation Supply Damper Inoperable This event was a result of mechanical binding of the damper and was corrected by lubrication and adjustment. This damper has been added to the preventive maintenance schedule to prevent recurrence. This LER is closed.
j.
LER 78-048 Core Flux Tilt Due To Uncoupled Control Rod The inspector reviewed this event with the licensee during inspec-tion 78-24 and has no further questions at this time. This LER is closed.
k.
LER 78-049 Relative Rod Position Indicator Inoperable This event resulted f rom improper termination at the reactimeter during perparation for special testing. The licensee has revised Perf ormance Test Procedure 110 to include verification of proper indication of cod position when connecting the reactimeter. This LER is closed.
1.
LER 78-050 " Duet Seal" in Cable Spreading Room Penetrations reviewed by the inspector and is discussed in This event was report 78-24. The licensee has removed the " Duct Seal" from all conduits located entire'y within the Cable Spreading room. This LER is closed.
LER 78-052 "B" Once Through Steam Gener'ator Level m.
Transmitter looperable This event was discussed with licensee personnel and the cause determined to be instrument drif t.
The inspector has no further questions at this time. This LER is close *
.
s
,
RII Report No. 50-302/78-29 I-6 9.
Review of LER Reporting Requirements The inspector discussed, with the licensee, the importance of accuracy and ampleteness in the description of events being reported via the LER sys ten (NUREG-0161). The inspector stated that cause codes and event descriptions must be accurate and complete and must contain information related to action taken to prevent recurrence. The licensee acknowledged the inspector's comments and indicated that all LER's would be screrned to itsur' accuracy and completegess.
10.
Facility Tours and Observations of Control Room Activities The inspector toured various areas of the Crystal River 3 facility to obse rve plant activities in progress, and to ascertain the general state of cleanliness and housekeeping. The inspector observed portions of plant activities on a daily basis that included two shifts.
The inspector observed portions of control room activities at various times during the inspection.
The inspector interviewed operations watchstanders, reviewed selected portions of logs and plant instrumen-tation, and verified compliance with Technical Specifications require-ments. No discrepancies were identified.