IR 05000400/1985026
| ML18019A299 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 07/03/1985 |
| From: | Conlon T, Gibbons T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18019A298 | List: |
| References | |
| 50-400-85-26, NUDOCS 8508080219 | |
| Download: ML18019A299 (10) | |
Text
RECIr
"o 0O A
~O
- ++
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 Report No.:
50-400/85-26 Licensee:
Carolina Power and Light Company 411 Fayetteville Street Raleigh, NC 27602 Docket No.:
50-400 Facility Name:
Harris
Inspection Conducted:
June 17-21, 1985 Inspector:c
'er~
.
D. Gi ons Approved b~
.
Con on, ection ie Engineering Branch Division of Reactor Safety License No.:
CPPR-158 Da e Signe Zs ate igne SUMMARY Scope:
This routine, unannounced inspection entailed 38.5 inspector-hours on site in the areas of instrumentation, procedures work activities, and quality documentation.
Results:
No violations or deviations wer e identified.
85080802l9 850708
't PDR ADOCK 05000400
.8 ":
..'DR r
C
'P
.J P
p 1
REPORT DETAILS Persons Contacted Licensee Employees
- R. A. Watson, Vice President, Harris Nuclear Project
- E. E. Willett, Instrumentation Manager
- R. L. Bryant, Instrumentation Supervisor
- D. A. McGaw, Superintendent, guality Assurance (gA)
- K. V. Hate, Principal gA Engineer
- A. H. Ragger, Manager, Construction Inspection
- B. R. Kramer, gA Surveillance Supervisor
- J. Wagoner, Electrical Engineer
- L. I. Loflin, Manager, Harris Plant Engineering Support NRC Resident Inspectors
- G. Maxwell, Senior Resident Inspector, Operations R. Prevatte, Senior Resident Inspector, Construction
- Attended exit interview Exit Interview The inspection scope and findings were summarized on June 21, 1985, with those persons indicated in paragraph 1 above.
The inspector described the areas inspected and discussed in detail the inspection findings listed below.
No dissenting comments wer e received from the licensee.
Unresolved Item 400/85-26-01 - Incorporation of Instrument Tubing Separation Criteria, paragraph 5.
Inspector Followup Item 400/85-26-02 -
Review of Studies on Tubing Separations, paragraph 6.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
Unresolved Items Unresolved items are matters about which more information is required to determine whether it is acceptable or may involve violations or deviations.
The new unresolved item identified during this inspection is discussed in paragraph I V
l
~
I
~ 4 K<<J
<< Il
4 f ~
>>
4
>>
JI P
f),', 4 r) II I>>
ft<<
(>>)
I)
<< I
>>r ">>4
)4>>>> )
Ji it> f
<<j
"~
)
~
'Vi I
~
>>
lil'>>>>
4 f>>
<<
>>
<<
5.
Instrumentation (Components and Systems)
-
Review of Quality Assurance Implementing Procedures (52051B)
The procedures which are used for the installation and inspection of instrumentation are:
Work Procedure WP-300 Instrument Work Package Revision 7 dated Preparation and Control January 8, 1985 Work Procedure WP-302 Installation of Supports Revision 5 dated for Safety/Seismic Related February 25, 1985 Instrumentation Work Procedure WP-304 Installation of Safety-Related and Seismic Process Tubing and Instrumentation Revision 4 dated November 2,
1984 Work Procedure WP-305 Installation of Tube Track/Impulse Line/
Instrument Identification Markers/Tags Revision 1 dated October 12, 1984 Technical Procedure TP-54 Inspection of Instrumen-Revision 4 dated tation May 13, 1985 Technical Procedure TP-67 Inspection of the Instal-lation of Seismic Class
and Seismically Designed Instrumentation Supports Revision 2 dated April 4, 1985 Corporate QA Procedure Instrumentation CQC
Inspection Corporate QA Procedure Mechanical Inspection CQC
Revision 3 dated June 4, 1985 Revision 12 dated February 11, 1985 The procedures were examined to assure that the requirements of identifica-tion, work procedures, specification requirements of independent isolation, separation and special installation instructions.
The procedures appear well written and acceptance criteria is incorporated.
The inspector identified that sensing line separation criteria is pot a quality inspection item.
The only reference to sensing line separation appears in WP 2, paragraph 3.6. 1.4.4 which requires
inch horizontal separation unless prior approval by Harris Plant Engineering Support (HPES).
Vertical separation is not specified.
The licensee is committed to Regulatory Guide 1.75 and IEEE Standard 384.
The licensee stated that the separation is considered during the design of the tubing isometric drawing and the separation is designed into the drawings.
The licensee's position will be transmitted to NRR for evaluation as to its acceptability.
This will be identified as Unresolved Item 400/85-26-01 - Incorporation of Instrument Tubing Separation Criteri Tt r'.,"
4 I y
P
)
I,
'1 T P>>P I
I t,
4>>
tttlr Ntwjp 1 llf 4>>f h
I,
"
lc fh
P
h
~ I II 4
[
-N th tl r
~
Il ItP>>'t
I.
")
.I TN.
Pw'hwlf
'
I tl r.
r
~,
~
r,w f I IP.
~
', rr
Nlt
ip pt r
C f4'p
'
~
"N, I
>>ll',
P
r
N
>>tr T
>>
I'
~
"P*h '
~
t PTT
~I't Nr r
t'P
'3 NIP p,
'
r'>>4 (P
-
.= f +
~
"
I I
4 4 t jf
,
N'
>T 1,'.t, P
.'PP.'
If
'IX r I
It P
p" *>>
P l(tl
'
. Ph, 1 -P,Y
~
h I
h I JP
'I j4 rh wp I
r V
'P'1
~ I
~
~
t
>>
P v
~,j
~ '"yf'..
Within the areas examined, no violations or deviations were identified.
Instrumentation (Components and Systems I) - Observation of Work and Wor k Activities (52053B)
The inspector selected two containment isolation valves, 2SI-V550-SB-1 and 2SI-V554-SB-1, a boric acid tank level transmitter LT-ICS-0161-SB-W, and three reactor coolant flow transmitter s, FT-01RC-414-I-W, FT-01RC-415-I I-W, and FT-01RC-416-III-W for examination.
The components were examined to assure that the FSAR and QC procedures were implemented in the areas of identification, location, supports, protection, inspection, QC records, physical separation, arid nonconformance control.
During the inspection of the core coolant flow transmitters, the inspector questioned several instances where the tubing appeared to have inadequate separation.
The drawings were reviewed and the installation was completed in conformance to design drawings.
The Harris Plant Engineering Section (HPES)
was contacted to ascertain what criteria should be used to define the tubing separation.
HPES stated that designer has verified, by study, that there is no common mode failure which could disable both tube trains.
The study was not available for review for these flow transmitters.
This item will be Inspector Followup Item 400/85-26-02 - Review of Studies on Tubing Separation.
Within the areas examined, no violations or deviations were identified.
Instrumentation (Components and Systems I) -
Review of Quality Records (52055B)
The inspector examined the QC records for the instruments identified in paragraph 6 above and the following additional instruments:
FT-01RC-424-I-W FT-01RC-425-II-W FT-01RC-426-III-W FT-01RC-434-I-W FT-01RC-435-I I-W FT-01RC-436-II I-W Reactor Coolant Flow Transmitters PT-01RC-455-I-W PT-01RC-456-I I-W PT-01RC-457-III-W PT-01RC-444-S-W PT-01RC-445-S-W Pressurizer Pressure Transmitters LT-01RC-459-I-W LT-01RC-460-II-W LT-01RC-461-III-W LT-01RC-462-S-W Pressurizer Level Transmitters
w M
K 1Iv I
l,t I
MX
~ l'
tt)
M,<<C
>>
1 I tl
>>
'45 zf 8" ff
-"h f<<
>>
I I
If
, II
>>
uil
1 1'
L
1 I 1 h
II I
,M M
it I
II'
t tu M
M)'
"M g
lI I
tt l.l IM f'
M
I
I
1'
It
>>11 th tt
~
l
~ 'l I.
',I
'Ig I', 'M f<< ~'J't>>
)- "uq Xf I ', '>>M)>>
,I f
>>
II X(
I "I II
~ t" V
~ >>
Mfu t
II tt
'
'1
II I <<>>
g
The inspector examined the-receiving inspection, material certification, storage, handling and identification.
The records for each instrument contained a receiving report, vendor certificate of compliance to the purchase order, gA release, certificate of cleanliness, hydrostatic test certification, vendor test report and material certifications.
The instrument is tagged for a specific plant location.
The warehouse was inspected to assure proper storage and handling.
The installation data packages for the above instrument contained a location arrangement sketch, stress calculations, bill of material, welding reports, nondestructive examination reports on welds, support details and inspections, torquing and final instrument inspection report.
The data packages for the following instruments were not complete at this time:
PT-ARC-0455-I-l, PT-01RC-457-III-W, PT-01RC-444-S-W)
PT-OlRC-445-S-W, LT-OIRC-459-I-W, LT-01RC-461-1 I I-W and LT-01RC-0462-S-W.
These packages were not complete because the support details and final instrument inspections were not complete.
Within the areas examined, no violations or deviations were identifie Ww
~
e tl I 'l
ll W
ll Il
~
I=
4 C
tf
~'4 ttl I
I
't II tl
"VW W'4 I
tl W
WW v,.