IR 05000369/1989042
| ML20006E598 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 02/07/1990 |
| From: | Cooper T, Shymlock M, Van Doorn P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20006E596 | List: |
| References | |
| 50-369-89-42, 50-370-89-42, NUDOCS 9002260097 | |
| Download: ML20006E598 (8) | |
Text
. _.. _ _ _. _ _
.,
,
%.:
W
..p tas UNITED STATES
'g-NUCLEAR REGULATORY COMMISSION -
,_
- ~
frj'
-1,8
[
REGION 11
?
- g --
j.
101 MARIETTA STREET,N.W.
?k
ATLANTA, GEORGt A 30323 '
%.... /
,
m Report Nos.: 50-369/89-42 and 50-370/89-42 Licensee: Duke Power Company 422-South Church Street
. Charlotte NC 28242 jj
~ Facility Name: McGuire Nuclear Station Units 1 and 2
. Docket Nos.::50-369 and 50-370 License Nos.: HPF-9 and NPF-17 Inspection Conducted: December 20. 1989 - January 22, 1990 Inspectors:
J/NdTM ch'l d' 7"96 P. K.-Van y rn..Sen16t Resident Inspector Date Signed
<
M'
yYb $
$~WO-T.Coope'r.R(fidentInsp66 tor Date Signed
d7dO Approved by:
M. B. Shymloc%f Chief Date Signed Reactor Projects Section 3A Division of Reactor' Projects-SUMARY Scope:'
This routine, resident inspection was conducted on site inspecting:in
~
the' areas of' plant operations safety verification, surveillance-
'
testing, maintenance-activities, followup-on previousTinspection
'
m
'
-findings and follov:up of event reports.
Results:
In. the areas inspected, one additional example of-af previous violation 'was identified. involving failure to write a Problem-Investigation Re concerning breakers with loose screws (paragraph 4.b.) port-e
,
<
+-
p
,
.
gF,
,
--
_......
..
_ - -
.
.. -
-
.
'
-.-
.
REPORT DETAILS q
1.
' Persons Contacted Licensee Employees
,
n
- G. Addis. Superintendent of Station Services
D. Baxter. Support Operations Manager J. Boyle. Superintendent of Integrated Scheduling D. Bumgardner.-Unit 1 Operations Manager J'.. Foster. Station Health Physicist
- D. Franks. QA Verification Manager i
G. Gilbert. Superintendent of Technical _ Services
- C. Hendrix Maintenance Engineering-Services Manager
- T. Mathews. Site-Design Engineering Manager
- T. McConnell. Plant Manager i
- D. Murdock McGuire Design Engineering Division Manager
R.-Pierce. IAE Engineer.
W. Reeside. Operations Engineer
,
R. Rider.. Mechanical Maintenance Engineer i
- M. Sample. Superintendent of Maintenance l
R. Sharp. Compliance _ Manager
- 1 t
J Snyder. Performance Engineer
<
J. Silver. Unit 2 Operations Manager A. Sipe. McGuire Safety Review Group Chairman
.i
- B.-Travis. Superintendent of Operations
Other licensee employees. contacted included craftsmen, technicians.
operators, mechanics, security force members, and of.fice personnel.
-i l
- Attended exit interview I
2.
P1antOperations-(71707.71710)-
I a.
The inspection staff reviewed plant operations :dur.ng the report
- i period to verify conformance with applicable regulatory requirements.
g Control room logs, shift supervisors' logs, shift turnover records
- l ard mipment removal and restoration records were routinely perused.
j Interviews : were conducted with plant ~ operations, maintenance, j
,_
chemistry. health physics,: and performance personnel.
'l
'
q Activities within the control room were monitored during shifts and
p at shift changes.
Actions and/or activities observed were conducted l
. as-prescribed. in applicable station administrative directives.
The j
complement of licensed personnel on each shift met or exceeded the
minimum required by Technical Specifications.
!
b.
Plant tours taken during the reporting period included, but were not j-limited to, the turbine buildings, the auxiliary building, electrical l
J equipment ' rooms cable spreading rooms, and the station yard zone inside the protected area.
l
,
,
-
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.
. _........
.....
.
.
"c.1
-
~
.
...
During' the plant tours. ongoing activities, housekeeping, security, equipment status and. radiation control practices were. observed.
While performing Auxiliary Building inspections, the inspectors ~ noted an improvement in the general cleanliness of the building.
There were still areas, however, that had some debris and equipment that sP needed to'be dealt with:
Outside of the Unit 2 Turbine Driven CA Pump room by the RN7A
-
valve, there were various tools and cleaning. equipment spread around on the floor.
On-the 767' elevations, in the room behind the YC pumps, debris,
-
such as L clothing. gloves.- cleaning bottles, and metal straps, has been collecting on top of the outage furniture stored'there.
On the 767' elevation, between the Unit 11/E fans and the wall,
-
a large amount of debris, such as tygon tubing, bottles, and metal: rods, has collected.
On the 767' elevation, by the Unit 1 Spent Fuel Pool Ventilation
-
.
fans, in an area marked. " NOTICE - This area has been designated-for: charcoal transfer equipment only". many pieces of equipment
' '
-other than charcoal transfer equipment are being stored, c.
Unit l' Operations'
'
The. unit began the inspection period at 100% power _and operated there
'
until January 8. 1990 '
At 1015 EST. on January 8. 1990, the "A" Feedwater_ Pump experienced a clogged control oil filter and' subsequently. ran back until it was' no-longer supplying feedwater to the Steam Generators.. While the operators were backing down load in anticipation of the transient, the "B" Feedwater Pump attempted to compensate' for the decrease in feedwater flow.
The Feedwater pumps both tripped on' a low suction pressure signal caused by the increased ~ demand without an increase in supply. This caused a turbine trip and'a subsequent reactor trip.
Following the turbine trip, the A.C. powered Bearing 011 Pump and the D.C.L powered Emergency Bearing 0111 Pump indicated that they weren running, but neither was developing any discharge pressure.
<
-Indications are that both the Bearing Oil Pump and the Emergency Bearing 011 Pump were air-bound. Plans had existed to provide' larger vent tubing for these pumps during the next scheduled outage, due to indications that the pumps had been cavitating.
'
a
,
.
aL Dic d'
s
.
]
.
]
'
,
.
The operators. secured the pumps and restarted them and finally
'
managed to develop discharge pressure on the Emergency Bearing 011-Pump.
.The turbine continued to coast down until it reached approximately 170 RPM. T At that point. -in less than 30 seconds, the turbine came to a' complete stop.
Subsequent investigation revealed damage to most of the bearings and some damage to the High Pressure turbine.
The utility entered the refueling outage. that had previously been scheduled for March-28
,
1990. On line date is scheduled to be April 28,1990.
,
d.
_ Unit 2 Operations The unit started the inspection at full power except.for a brief period of time when the unit commenced load reductior. to 86 percent power on January 21, 1990 for load folicwing, the unit reached full power on January 22, 1990.
No violations or deviations were identified.
?
3.
SurveillanceTesting(61726)
i Selected ' surveillance tests were. analyzed and/or witnessed by the;
-
s inspector to ascertain procedural and performance adequacy and conformance I
with applicable Technical Specifications.
i Selected tests were_ witnessed to ascertain.that current written approved procedures were available and in use.- that test equipment in use was l calibrated, that test prerequisites were met, that system restoration was
>
completed and acceptance criteria _ were met.
l
,
Detailed below are selected tests which-were either reviewed or' witnessed:
-
h Pfocedure Equipment / Test
,
i PT/2/A/4252/01 Auxiliary Feedwater Pump #2 Performance Test
]
PT/0/A/4600/02A Incore and Nuclear Instrumentation
'
Systems Correlation Check PT/2/A/4200/25 IWP Pump-Testing - Monthly
^
PT/1/A/4209/01A Centrifugal Charging Pump 1A Performance Test
"
PT/1/A/4600/03C Weekly Surveillance Items
,
PT/2/A/4200/06B Boron Injection Valve Lineup i
Verification PT/2/A/4200/288 B Train Slave Relay Test i
,
i
,
-.
..
l
.:
'
.
,
Procedure Equipment / Test (Continued)
.
PT/1/A/4450/03C Annulus Ventilation System Performance Test-4.
Maintenance Observations (62703)
a.
Routine maintenance activities were reviewed and/or witnessed by the resident inspection staff to ascertain procedural and performance adequacy and conformance with applicable Technical Specifications.
The selected activities witnessed were examined to ascertain that, where applicable current written approved procedures were available and in use. that prerequisites were-met, that equipment restoration was completed and maintenance results were adequate.
Activity Work Request / Procedure Observe Acoustic Monitoring N/A nf. Main Feedwater Check Valves 1 & 2CF-25.26.27 and 28 Inspect Spare Breaker #5A 69765 / IP/0/A/3850/09.
on Motor Control Center 1EMXH Preventive Maintenance 01964B / MP/0/A/7300/01 on Containment Spray Pump 2B Preventive Maintenance 07722A / MP/0/A/730/01 on IB ND Motor No violations or deviations were identified, b.
On-January.17.1990.- Catawba Nuclear Station notified the plant-tnat they had. identified a generic concern with the screws used to hold the moveable contactors in place in-600 V safety-related breakers.
These contactors were manufactured by GTE:Sylvania and had been in use in the plant since construction. The contactors in question were sSylvania model TM. sizes 00. O.1. and 2.
The screws used to hold the contactors in place had a tendency to loosen over a period of time, due mainly to vibration.
GTE Sylvania supplied correspondence to the licensee that demonstrated that they had identified this problem-in 1980.
In 1982 General Motors was notified of the problem and the needed solution'
was described in the letter to them.
These breakers.are are'a commonly used item in several industries, including the nuclear industry..
GTE Sylvania has not previously notified the nuclear industry.of the potential problem with the screws.
y i
,
.
_
._
_
m
.
"
"
.
.
g
.,
m
,
.
!
The licensee dnitiated an inspection of the 34 safety-related MCCs
'
whh;h utilize this type of breaker.
Thirteen breakers with loose
,
screws were identified.
These screws were removed and.the contacts were inspected.
The screws were replaced and torqued -to twenty
~
i inch-pounds, as ' recommended by the manufacturer.
The licensee
performed an operability evaluation on all'of the breakers with loose
screws and determined that they had remained operable at all times.
'
~ The licensee plans to replace all of the screws in the safety-related -
J breakers with nylon coated screws, which were designed to prevent <
loosening due to vibration.
The licensee indicated that they were aware of a tendency for these screws-to vibrate loose. 'even though they had not been infomed of
.such by the manufacturer.
During the routine preventative
'
maintenance, the technicians would tighten those screws found loose, as directed by the PM procedure.
Even thcugh the technicians'were aware of.the potentially loose screws, no Problem Investigation Report was -issued. which would have identified and evaluated the problem at an earlier stage.
The lack of documentation of the
' identified - problem with a PIR is considered another example of
~
violation 369. 370/89-01-07. Failure ; to Follow Procedures with Respect to' Problem Investigation Reports. which is presently an open issue.
The licensee indicated that-they would review the.previously intended corrective action in light of the new example and respond to the violation if additional' corrective actions are deemed necessary.
5.
Licensee Event Report (LER) and Part.21 Followup (90712,92700)-
(Closed).Part-21 369/87-01:
Inadequate High. Temperature' Resistance of Rockbestus' Coaxial Cable Insulation Located on Sorrento:High Range Rad y
Monitors.
The inspector-verified that the licensee had received-the-
'
reportJand-had -initiated appropriate corrective action.
Licensee
evaluation documented 'in Problem Investigation Report (PIR) M87-0042 -
i showed their cable to be acceptable.
,
(Closed) Part 21 369.370/89-12: Limitorque Corporation SMB-000 and SMB-00 Cam Type Torque Switches Can fail as a Result of Stationary Contact Screws Loosening.
The inspector -verified that the licensee had received the
,
report. and had initiated corrective action.
Corrective action has been
,
' initiated to ' replace the affected switches and is documented in PIR
!
-
M89-0293.
,
No violations or deviations were identified.
6.
Followup on Previous Inspection Findings (92701, 92702)
The following previously identified items were reviewed to ascertain that
,
,
-the!11censee.'s responses, where applicable, and licensee actions were in compliance with regulatory requirements and corrective actions have been completed.. Selective v
~ ~ ;t iacluded record review, observations, and discussions with '
grs", '.
.
.
>
<
t
.
-
-
....
-
--
..
,
t.
4m
,
,
'
A j
'
j
,
u G
.
,
,
i a.
(Closed)' Unresolved Item 370/87-14-02: Diesel Operability in Manual Mode. This item questioned whether logging the Diesel Generator (DG)
J
?
inoperable when-an out of service pressure switch caused the_ manual
' start feature to be' inoperable was appropriate. Also in question was the actual operability of the DG in this condition.
The licensee
,
reviewed this event and determined that the DG would have functioned
'
per the accident basis.
However, the licensee -indicated that:it
'
'
would have been appropriate to log the DG inoperable and feels that this.would be typically done in the current time frame. A violation
. was issued -in the time frame of the event for failure to log inoperable items.
The inspector discussed the licensees evaluation
<-
and reviewed Operations Management Procedure 2-5:
Technical Specifications Action Item Logbook, s
b.
-(Closed)
Inspector Followup Item 370/87-21-01:
Review PIR M87-151 Re_ Inadvertent-SI While Realigning from NC Check Valve Test.
-
Appropriate corrective actions: have been completed _ and are documented l
in PIR.M87-151.. These include counseling of the operator involved
'
and review of procedures for changes which resulted in changes to
'
test procedures. Licensee actions appear to be appropriate.
c.
(Closed)
Inspector Followup Item 369,370/87-41-01:
Non-Existent I
Program for Control of Auxiliary Building Pressure Boundary Doors.
'The licensee-does have a program which includes signs on the doors,
,
periodic - maintenance and periodic testing.
However, doors have
L, occasionally. been found open recently.
The licensee evaluated this
"
problem and determined that retraining would be accomplished. in the o
,
short term.
Hardware fixes such as stronger closures are. difficult
,
l since the direction of pressure-differential varies and also a ventilation-system modification' is' in progress. The ; licensee.
indicated that hardware modifications <would continue to be pursued as-i a possible'long' term fix.
Licensee actions appear appropriate.
-.
U d.
I(Closed)- Inspector Followup Item 369,370/88-31-25:
Verify Design -
Engineering Procedure Improvements for 10 CFR 50.59 Evaluations.
The
.
inspector reviewed the Design Engineering procedure and verified that j
revisions have been incorporated to ensure that any changestto the-original modification scope will require performance of a new 10 CFR 50.59 evaluation.
-
e.
(Closed)
Non-Cited Violation 369,370/89-01-05:
Followup on-i
__
Improvements in Control. Room Drawing Control.
The licensee has
{c
. implemented corrective actions which included implementation of an
-
improved distribution-system, personnel training, deletion of some ~
unneeded drawings, correcting the deficient drawings, implementing a QA audit, revising - the drawing control procedure (OMP1-11:
Operations Modification Implementation Process), benchmarking current status of limited edition, prints and development of a temporary modification logbook.
The-inspector verified these correctdve actions and reaudited a sample of 18 Control Room and Technical
'
Support Center drawings. ' No additional problems were identified.
,
,
s
=
.
.
.
.
,
~
-
-
' ~
'
,.
3;.
..,
,
'
i
,
L'
f.
(Closed)
Inspector Followup Item - 369.370/89-18-02:
Review of
.
Licensee Evaluation of Control Room Door Problems.
The licensee evaluated the effect of a' control room (CR) door seal degradation on
'
o CR ventilation operability and documented this review on PIR M89-156.
,,
The event' was determined - to not be ' reportable.
The licensee also
'
issued a Technical Specification interpretation to provide guihnce for' actions to take when doors are found degraded.
The inspector reviewed the PIR-and interpretation.
r No violations or deviations were identified.
L 7.
ManagementMeetings-(94702.30702)
The inspector participated in two management meetings held during. the
inspection period..The first was held on January 9.1990: to discuss Intersystem LOCA precursor and related events and the licensees corrective
,
actions planned or taken.
Events discussed included overpressurization of
Chemical and. Volume Control System piping. air binding of a Residual Heat i
Removal pump. Safety injection check valve. failures and overpressurization
,
.of. Containment Spray System.
The licensee also discussed the potential
impact of NRC Generic Letter 89-10:
Safety-Related Motor Operated Valve Testing and Surveillance on these types of events and'the Probabilistic Risk l Assessment aspects of Inter system LC#A events.
!
The second - meeting. was held on January 16-17. 1990 to discuss the licensee's. fitness for duty program, handling of-discrepancies as. they-affect operability and/or. licensing basis, and status of various licensing i-t issues. Minutes of both meetings will be issued by NRC/NRR.
8. -. Exit' Interview (30703)
.
The inspection scope and findings identified below.were sumarized on j
. January 22,1989 'with those persons indicated in paragraph 1 above. The-following item as discussed in detail:
,
,
The additional example of a previous violation involving.. failure to
.
' document loose screws in breakers.
-l
'The licensee: representatives present offered no dissenting comments, nor.
a did they identify as proprietary any of the infonnation reviewed by the inspectors during the course of their inspection, y
',
s
i
+.
t
.t
,
'
>
.
.
'
.
-
- - -
-
-
.