ML20127E623
| ML20127E623 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 04/15/1985 |
| From: | Conlon T, Miller W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20127E562 | List: |
| References | |
| 50-369-84-20, 50-370-84-17, NUDOCS 8505200135 | |
| Download: ML20127E623 (7) | |
See also: IR 05000369/1984020
Text
'
'
J:}-;;
,
.
- >RKEff
UNITED STATES '-
,
. c{
'
NUCLEAR REGULATORY COMMISSION
'
f[
REGION il
p.
- g-
y1
1101 MARIETTA STREET,N.W.'
-
. *
- .'
' ATLANTA, GEORGIA 30323
s
+4.....
-
-Report Nos.: '50-369/84-20 and 50-370/84-17
Licensee: Duke Power Company.
>
422 South Church Street
e
LCharlotte, NC 28242
>
. Docket Nos.:' 50-369 and 50-370
License Nos.:
<
.-
.
v
_ * Facility Name: McGuire 1 and 2
i
,
f*
' Inspection Conducted: September 4-6,.1984
-
,
7#[w
'/ - / 3'- f(
Inspector:
- 2
-
- -
W. H. Miller, Jr.
I
Date Signed.
o
? pproved by:
dP s w
T-/5'-f(
'
'
A
7
'
e
^^
T. E. Conlon. 5ection Chief
Date 51gned
',
'
.
.
Engineering Branch
-
'
.
g ' ;.
Division of Reactor Safety
,
. < -
,
?. i
' '
>
,
/
a
,
. = .
. j- .
.
'
'
,
-
<
-
SUMMARY
-
'
- i p . , Scope: . This' routine, unannounced inspection. involved 20 inspector-hours on site
.
.
.
.
..
.
,
-in the areas of Fire Protection / Prevention and Standby Shutdown Facility System.
.
,
Resul'ts: One violation was identified - Failure to Perform Periodic Tests of the.
'
r
.
' ' Standby Shutdown System - paragraph 5.b.
t
'
.
,
l
,
,7
,
l-
>
h.
'
.L'
('
i
1 -
!,
t
8505200135 850419
-
'
ADOCK 05000369
G
'
,
I
t-t
ew
-'-w-e
-*-w
e,
e
-
ev
-,-w-
e e -w w - e-
.----ww-rw
e- w
+*-,rm',e-+--w-*-,--+-*
~ - - + -
--+---w-,,=,-,==w-----.--*<-~,-w+--
=-
--w-we-
e
-v
'
.
REPORT DETAILS
1.
Licensee Employees Contacted
- M. D. McIntosh, Station Manager
- K. S. Canady, Manager, Nuclear Engineering Service
- R. L. Gill, Licensing
- D. Mendezoff, Licensing
- D. Hyde, Operations
R. Pierce, I&E Engineer
- W. E. Galbreath, Performance
- L. R._Kimray, Chemistry
- R. F. Turner, I&E Engineer
NRC Resident Inspectors
'
- W. Orders
- R. C. Pierson
- Attended exit interview
2.
Exit Interview
The inspection scope and findings were summarized on September 6,1984, with
those persons indicated in paragraph 1 above.
The following item was
identified to the licensee:
a.
Violation Item (369/d4-20-01 and 370/84-17-01), Failure to Perform
Periodic Tests of the Standby Shutdown System - paragraph 5.b.
b.
Inspector Followup Item (370/84-17-02), Calibration Records Not Avail-
able for Standby Shutdown Facility (SSF) Steam Generator C and D Level
Instruments - paragraph 5.b.(4).
The licensee did not identify as proprietary any of the material provided to
or reviewed ~ by the inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters
Not inspected.
4.
Unresolved Items
Unresolved items were not identified during this inspection.
'5.
Fire Protection / Standby Shutdown System
A review was made of the Standby Shutdown System (SSS) and systems provided
-since- January 1983, to meet the dedicated plant shutdown fire protection
requirements of 10 CFR 50, Appendix R, Section III.G.
Operating License
-
-
- .._
2
Section ' 2.C.(4) for Unit I and Section 2.C.(7) for Unit 2 require the
licensee to maintain in effect and fully implement all provisions of the
approved fire protection plan and the Fire Protection Review in Supple-
ments -5 'and 6 to the McGuire Safety Evaluation Report (NUREG-0422). The SSS
System which is part of the McGuire fire protection progran was required to
be operational by January 28, 1983, for Unit 1 and prior to March 1, 1984,
for Unit 2.
However, since Unit I was in an outage until April 29, 1983,
the -SSS~ for Unit I was not required to-be operational until the end of this
outage.
The following items of the SSS and associated systems were evaluated:
-a.
-Operational Procedures
-The following procedures were reviewed and it was verified that these
procedures were issued prior to the date the SSS was required to be
operational:
'
No.
Title
OP/0/A/6100/17
Operation of the Standby Shutdown
Facility
OP/0/B/6350/04
Standby Shutdown Facility Diesel
Operation
AP/1/A/5500/17
Loss of Control Room
AP/2/A/5500/17
Loss of Control Room
b.
Surveillance and Maintenance of Standby Shutdown Facility
A review was made of the following surveillance inspection, test and
E-
maintenance records for the dates indicated.
I
(1) PT/0/A/4200/02, Standby Shutdown Facility Operability Test
(31 days)
!
(a) Unit 1 SSS Operability Tests
!
l-
The SSS for Unit I was required to be operational on
>
January 28, 1983. However, Unit I was shutdown for an outage
l.
from January 21: to April 29, 1983.
The first operability
i
test of the SSS was conducted on April 28, 1983, which
[
demonstrated that the Unit 1 portion of the SSS was. opera-
l
tional, except the instrumentation devices for the reactor
coolant wide range pressure, pressurizer level and steam
'-
generator levels did not meet the acceptance criteria of
,
Procedure PT/0/A/4200/02.
l
-
.
]
m
,
~
,
...
~3
-
The 1_icensee's operability tests, conducted during several
. months ~ of 1983, and 1984, found the' SSS instrumentation
' devices either inoperative or out of the tolerance permitted
by .the procedure.
For example, the steam generator level
gages were found out of tolerance on September 15, 1983, and
t -
' were not repaired until June 12, 1984.- The-SSS pressurizer-
level gages were found inoperative on September 15, 1983, and
-were not- repaired until - August 11, 1984.
The incore
thermocouples were found nonfunctional on September 15, 1983,
and were not repaired and retested until June 12, 1984.-
The diesel engine for the emergency SSS generator reportedly
was out of service on several occasions due to maintenance,
repairs, and testing operations.
The engine was out of
service - October 11-14, 1983,-' to replace the oil filter,
-
October 19-26, 1983, to repair and/or replace the voltage
regulator. and engine governor, and from February 14 to
March 29,1984, due to engine testing and correction of
overcurrent trip problems.
Unit I was operational during
these dates except for the _ refueling outage which began
February 24, 1984.
(b) Unit 2 SSS Operability Test
The SSS for Unit 2 was required to be operational prior to-
March 1,1984.
Tests records from April 28, 1983 through
August 11, 1984 were reviewed.
Routine operability tests of
the SSS components for Unit 2 were conducted on April 28,
1983, prior to the required time, and monthly thereafter,
except operability tests were not conducted from January 16
!
through - April 24, 1984. - Unit 2 was operating during March
and April of 1984.
The licensee's operability tests, conducted during 1983 and
1984, found the SSS instrumentation devices either inope-
rative or out of the tolerance permitted by the procedure.
'For ' example, the SSS pressurizer level gage was found
inoperative on May 13, 1984, and was not repaired until-
August 21, 1984.
The incore thermocouples were found
nonfunctional on September 15, 1983, and were not repaired
and retested until June 12, 1984.
The diesel engine for the emergency SSS generator reportedly
was out of service on several occasions due to maintenance,
repairs, and testing operations.
The engine was out of
service October 11-14, 1983, to replace the oil filter,
October 19-26, 1983, to repair and/or replace the voltage
regulator and engine governor, and from February 14 to
March 29,1984, due to engine -testing and correction of
overcurrent trip problems.
The SSS was required for Unit 2
beginning March 1, 1984.
r
i
_
..;
4
(2) PT/1/A/4209/0/1C, Standby Makeup Pump Flow Periodic Test (92 days)
Test records of April 25, 1984 to July 24, 1984, were reviewed.
The -first recorded operability test of the Unit 1 Standby Makeup
Pump following turnover to the plant's operations group on
' January 26, 1983 was April 25, 1984. This pump was required to be
in service by- January 28
1983.
The failure to verify the
operability of this pump periodically in accordance .with
PT/1/A/4209/0/1C is identified as Violation Item (369/84-20-01),
Failure to Perform Periodic Tests of the Standby Shutdown System.
Operability tests conducted by the licensee on this pump during
August 1984, indicated that the pump would only deliver approxi-
mately 22 gpm against a head pressure of 2485 psig in lieu of the
-required 26 gpm at a pressure greater than or equal to 2485 psig.
To correct this deficiency required the following modifications:
Rebored and increased damper orifice from 1.16 to 1.2484 inch
-
diameter (NSM No. MG 1-1613 and Work Request No. 93145);
Replaced valve INV845 with another type gate valve and added
-
a pressure gage to permit the pump to be tested under a back
pressure of 2485 psig (NSM No. MG 1-1673 and Work Request
No. 93156);
Replaced pressure relief' valve INV843; and,
-
1
l
Changed size of motor sheave (pulley) from eight to nine
-
inches diameter to~ increase capacity output of the pump (NSM
No. MG 1-1674 and Work Request No. 93157).
Subsequent tests indicated that this pump would deliver 29 gpm at
2485 psig which exceeds the minimum requirement of 26'gpm.
(3) PT/2/A/4709/0/1C, Standby Makeup Pump Flow Periodic Test (92 days)
Test records of June 15, 1983, to May 25, 1984, were reviewed.
This pump was not required to be operational until March 1, 1984.
Operability tests. conducted by the licensee on this pump during
August 1984, indicated that the pump would only deliver 22 gpm
against a head pressure' of 2485 psig in lieu of the required
26 gpm.
To correct this situation, the licensee accomplished the
same above modifications required for the Unit 1 pump. This work
was accomplished under the following Modification / Work Request
Nos.: MG 2-469/WR 93115, MG 2-524/WR93154, and MG 2-525/WR 93158.
Following these modifications, the pump was retested and delivered
30 gpm against a head pressure of 2485 psig.
.
,.
_
,.
,
5
(4) IP/0/B/3250/08, Instrument Calibration (18 months)
The calibration- dates listed by the licensee's Periodic Mainte-
nance Program documentation records for the following instruments
were reviewed:
Date of Calibration
-Device No.
Function
Unit 1
Unit 2
NCLP5121
Reactor Coolant Pressure
4/20/81
1/6/84
4/27/84
NCLP5151
Pressurizer Level
4/20/81
1/9/84
11/20/82
4/6/84
CFLP6080
Steam Generator "A"
4/1/81
5/6/83
Level
3/1/84
ENALP9110
Incore Thermocouples
4/20/81
2/20/84
11/23/83
Procedure requirements- for calibration of SSS instrumentation
devices, including, reactor coolant pressure, steam generator
level and incore thermocouples, within 18 months following the
initial calibration were not adhered to for Unit 1.
The time
between calibration was 36 months for reactor coolant pressure
devices. 35 months ~ for steam generator level devices, and
31 months for incore thermocouples. This is identified as another
example of Violation Item (369/84-20-01).
The calibration records for the Unit 2 SSS instruments for the
level within steam generators
"C"
and "D" could not be located.
Pending the licensee's research, location, and NRC review of these
records, this item is identified as Inspector Followup Item
(370/84-17-02), Calibration Records Not Available for SSF Steam
Generators "C" and "D" Level Instruments.
(5) IP/0/B/3061/02, Station Auxiliary, Standby Shutdown Facility Power
Batteries (Monthly)
The licensee's record data indicated that the SSS batteries were
inspected monthly from December 3,1982, to August 27, 1984,
except an inspection was not performed between September 9, 1983,
and November 28, 1983. Unit I was operating during this time.
Surveillance of the diesel engine starting batteries for the SSF
generator was not initiated until November 11, 1983. The SSF for
Unit I was required to be operational by January 28, 1983.
Monthly- inspections have been made of these batteries since
November 1983.
However, the failure to conduct monthly inspec-
.-
,
6
tions of these batteries
example of Violation Item (prior to November 1983, is another
369/84-20-01).
Procedure for detail periodic inspection and maintenance of diesel
_ generator starting batteries to verify such items as battery-to-
battery terminal connections are clean, tight, and free of
corrosion had not been issued.
This is another example of
ViolationItems(369/84-20-01and370/84-17-01).
(6). Diesel Fuel for SSF Diesel Engine
The licensee stated that new fuel received and placed in the fuel
storage tank for the diesel engine to the- SSF generator was
received and sampled, the same as the fuel for the main station
emergency diesel driven generators. Records were not available to-
substantiate this statement, but it appears that this was true.
However, procedures were not provided to periodically verify that
the diesel fuel in the diesel generator fuel storage tank is
within acceptable limits when checked for viscosity and water and
sediment.
This is another example of Violation Items
(369/84-20-01and370/84-17-01).
(7) Water Supply to Standby Makeup Pumps
The water in the Unit 1 fuel pool is sampled every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to
verify that the boron concentration remains equal to or greater
than 2000 ppm.
This should assure that the water to the makeup
pump will contain the minimum required boron concentration.
The
water for the Unit 2 standby makeup pump was obtained from the
wier wall enclosure within the Unit 2 fuel pool area. This water
reportedly was supplied from the Unit 2 reactor water storage
tank; however, no records were available to indicate that prior to
September 5,1984, periodic water samples had been obtained to
verify that this water contained at least a minimum baron
concentration of 2000 ppm.
Apparently, a procedure to require a
periodic sample of this water was not available.
This item is
identified as another example of Violation Item (370/84-17-01).
Other than the above listed violation, no additional violations or devia-
tions were identified within the areas examined.
!