IR 05000285/1978014
| ML20062G586 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/20/1978 |
| From: | Boyter N, Johnson W, Verduzco G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19263A708 | List: |
| References | |
| 50-285-78-14, NUDOCS 7901020131 | |
| Download: ML20062G586 (9) | |
Text
,
U. S. i;UCLEAR REGULATORY COD 11SSION OFFICE OF IllSPECTION AliD ENFORCEi1ENT REGI0il IV Peport tio. 50-235/78-14 Docket lio. 50-285 License fio. DPR-40 Licensee: Omaha Public Power District 1623 Harney Street Omaha, liebraska 63102 Facility flame: Fort Calhoun Station, Unit 1 Inspection At: Fort Calhoun Station, Blair,itebraska Inspection Conducted:
October 23 >~ and tioverrber 1-3, 1978
-
Inspectors:
C/ O 7 /,1n m 1%-/,e W. D., Johnson, Reactor Inspector Date
.
kS~'
H b'/SE fl. C.' Boyter, ReactQr Inspector Date b
MW tl[1['Ti
-
G. H. Verduzco, % actor inspector Date
.'\\v(! [ t.,
.
Ilfil[F
1 -
L. D. Gilbert,1 Reactor Inspector Date
'
t a
>
\\,'
,, -
_
0.. _ !LL r ! f /qc r
{. s D. P.:Tomlinson, Reactor Inspector (Training)
Dat.e i Li d
Approved By:
.
!
E' ^ '-
' ' /c 7e
'G. L. 'tadsen, Cnief, Reactor Operations anc Date fluclear Support Branch 790102ca(
P
.
-2-
.
Inspection Summary
Inspection on October 23-27 and t!ovember 1-3.1978 (Report tio. 50-285/78-14)
i Areas Inspected: Routine, unannounced inspection of preparation for refuel-ing; refueling activities; surveillance of pipe support and restraint systems; and inservice inspection program, procedures, work activities and records.
The inspection consisted of 158 inspector-hours on-site by five (5) tiRC inspectors.
Results: Of the four areas inspected, no apparent items of noncompliance or deviations were identified in three areas and two apparent items of non-compliance (infractions) were identified in one area (Failure to _ include appropriate acceptance criteria in a surveillance test procedure and failure to perform required visual inspections of hydraulic shock suppressors -
paragraph 6).
>
I I
l i
'
s l
[
.
.
.
'
.
-3-
,
DETAILS 1.
Persons Contacted a.
Omaha Public Power District Personnel
- R. L. Andrews, Plant Managar R. C. DeMeulmeester, Shift Supervisor L. J. Ougger, Reactor Engineer R. G. Fleischmann, Operations QA Engineer J. F. Gass, Training Coordinator W. G. Ga tes, perations Supervisor B. J. Hickle, Licensing Assistant D. W. Jones, Maintenance Supervisor
- R. C. Kellogg, Senior Engineer
- L. T. Kusek, Technical Supervisor M. J. McFadden, Plant Engineer M. McEwan: Test Engineer M. L. Meador, Shif t Supervisor K. J. Morris, Manager, A67tnistrative Services J. C. Riely, Shift Supervisor D. Rollins, Test Engineer G. J. Pelnar, Shift Supervisor S. C. Stevens, Manager, Operations Technical Support Services C. F. Vanecek, Snift Supervisor b.
Combustion Engineering Personnel J. P. Larean, Senior Development Engineer c.
Southwest Research Institute Personnel C. L. Cotton, Project Engineer D. F. Rosow, Manager, Nuclear Field Service Section C. E. Trout, Team Leader
- Attended exit interview.
l'
employees during the inspection.
These included reactor operators, The inspectors also talked with and interviewed several other licensee maintenance technicians and office personnel.
2.
Prenaration for Refueling Continuing the inspection effort which was started during a previous inspection, the inspector rev;ewed Operating Procedure OP-ll, Revision 1, dated October 31, 1978.
This procedure was in use as the controll-ing document for fuel handling activities.
No items of noncompliance or deviations were idantifie _
. _ _.
.
.
.
.
}
-4-
3.
Refueling Activities a.
Preliminary Activities
,
The inspector rade direct observations and reviewed records as necessary to verify compliance with the surveillance testing, procedural and Technical Specification requirements associated with the following pre-refueling activities:
(1) Refueling machine pre-ooerational tests (2) Spent fuel handling c2. hine pre-operational tests (3) Fuel storage area ventilation (4) Crane testing
(5) Refueling deck radiation monitors (6) Comnunications systems (7) Stored fuel cooling b.
Fuel Handling Activities The inspector made direc t observations and reviewed records as necessary to verify existence of the following conditions and to verify that the activities were conducted as required by Technical Specifications and approved procedures:
(1) Containment integrity was properly set.
s (2) The required containment atmosphere and plant ventilation direct radiation c.onitors were operable.
(3) Radiation levels in the containment and spent fuel storage areas were monitored as required.
(4) fieutron flux was monitored as required.
'
(5) One shutdown cooling pump and heat exchanger were in opera tion.
(6) The reactor coolant system and the spent fuel pool were sampled at the required frequency and boron concentration was found to be in compliance with Technical Specification requirements.
,
_
.
.
"
-5-(7) Communications between the control roca and the refueling machine were maintained as required by the Technical Specifications.
(8) Exhaust ventilation from the spent fuel storage area was diverted through a charcoal filter when irradiated fuel was being handled in the auxiliary building.
(9) Refueling pool water level was maintained as required.
(10) Fuel assembly insertion and removal from the core was perform-ed in accordance with Operating Procedure OP-ll and Operating Instruction 01-FH-1.
(11) Control room activities associated with fuel assembly inser-tion and removal were performed in accordance with OP-ll.
(12) Core internals, the reactor vessel head, studs, nuts, and washers were stored properly.
(13) Fuel accountability mathods wer? in accordance with OP-il and Nuclear Materials Accountability Procedures Nos. 1 and 3.
(14) Housekeeping on the refueling deck was in accordance with Standing Order 0-35.
(15) The makeup and license requirements of the refueling crew on the refueling deck and in the control room were in accord-ance with Technical Specification 5.2.2.
c.
Findings No items of noncompliance or deviations were identified.
4.
Meeting with NRC/NRR and OPPD
'
The inspector toured portions of the auxiliary building and containment witn representatives of NRC/NRR and the licensee, and attended confer-ences with these groups. The subject of the discussions was the
,
'
possible testing or inspection of check valves SI-159 and SI-160. These valves are in the safety injection recirculation lines between the containment sump and the suctions of the safety injection pumps.
,
,
-.e
-
--
- -,
.
.
-6-5.
Hydrogen Purge Syster During a review of Operating Instruction 01-VA-1, the inspector noted that section IV.H.3 does not specify the desired valve lineup for tho weekly operational test of the hydrogen purge fans, VA-80A and VA-808.
The inspector discussed this item with a licensee representative, who indicated that the procedure would be revised.
(0 pen Item 285/255)
6.
Surveillance of Pipe Support and Restraint System The inspector conducted an extensive visual examination of shock suppressors and restraint systems both inside and outside of contain-ment. A rev'aw was conducted of the five new surveillance test pro-cedures whicn replaced the previously used maintenance procedures for inspection and testing of hydraulic shock suppressors (HSS). The licensee's records of follow-up actions on the reported 15 inoperable
shock suppressors in fiovember 1977 were reviewed for completeness.
The.
results of the functional testing, which had not been performed at the time of the inspection, will be reviewed during a later inspection.
(0 pen Item 285/256)
During the visual examination, the following significant items were noted and discussed with the licensee:
The cormion reservoir for HSS RCP 3A and 4A had no oil visible
.
in the sight glass.
The charging pump valve roon appeared to have had some piping support modifications.
Licensee representatives were not aware of the status of this apparent design change.
The pipe support next to the discharge relief valve of "A"
.
charging pump had one side broken off.
The pipe support next to the suction relief valve for the "C"
.
charging pump had one end broken off.
The bolts were missing on one of the anchor plates of a pipe
.
support bracket on "B" charging pump suction pipe in the valve room.
These items have been grouped together as Open Item flumber 285/257.
Surveillance Test Procedure ST-HSS-5 (Surveillance of Grinnell Hydraulic Shock Suppressors Reservoir Oil Levels in Containment) does not contain any acceptance criteria for the reservoir oil levels. A review of the records of the test indicates that this lack of acceptance criteria caused some inconsistency in evaluating the results for determining the next inspection interval.
The inspector discussed with a licensee rep-resentative the need for improved analysis of results to accurately
-
.
,
.
.
'
-7-determine the next inspection interval. The licensee's failure to include acceptance criteria in ST-HSS-5 is an apparent item of non-compliance with Criterion V of Appendix B to 10 CFR 50 as amplified by Section 17.5 of the licensee's NRC approved QA Program.
LER 77-30 reported 15 of 24 Grinnell shock suppressors inoperable due to low fluid level in November 1977 and invoked the increased inspection interval of 31 days as required by Section 3.14(1) of the Technical Specifications. The records of these inspections (ST-HSS-5)
on the dates November 23, 1977, January 6,1978, February 10, 1978, March 31, 1978, May 17, 1978 and September 8, 1978 document only the inspection of reservoir fluid levels.
Since these reservoirs are remotely located from the suppressors and, in most cases, one reservoir supplies more than one suppressor, a visual inspection was not performed on each of the Grinnell shock supppressors as required by Section 3.14(1)
of the Technical Specifications.
Their failure to make visual inspections of all Grinnell shock suppressors on the increased inspection interval following the November 1977 inspection of the suppressors is an apparent item of noncompliance with Section 3.14(1) of the Technical Specifications.
7.
Inservice Inspection a.
Review of Progs.a and Procedures The inspector reviewed the licensee's program for inservice inspection of the steam generator tubes, reactor coolant system, and safety related piping systems. The licensee's program includes a Special Procedure, SP-RC-2, to control Eddy Current Testing of steam generator tubes and a Surveillance Test, ST-RCS-1, to control RCS inservice examination.
In the areas of the licensee program reviewed, no discrepancies with the requirements of Section XI to the ASME B&PV Code were noted.
The inspector reviewed the CE Procedure for Eddy Current Testing of steam generators (Procedure 00000-NLE-082-07) for compliance with Regulatory Guide 1.83, and SwRI Procedure for Liquid Penetrant Examination (SwRI-NDT-200-1-R42) for compliance with Section V of the ASME B&PV Code.
In the areas inspected, no discrepancies were noted.
No items of noncompliance or deviations were identified.
b.
Observation of Work Activities (1)
Inspection Interval and Extent of Examination The inspector reviewed the licensee's Project Plan (SwRI Proj ect 17-4145) for inservice inspection during the 1978 (fif th) outage for compliance with scheduled examinations
,
-.
~,--s
-
.
.g.
required in the Ten Year Inservice Inspection Plan (SwRI Project 17-4551).
The scheduled examinations reviewed were consistent with the Ten Year Plan and the ASME B&PV Code Section XI requirements.
flo items of noncompliance or deviations were identified.
(2) flondestructive Examination Personnel Qualifications The inspector reviewed the certification records for all eight on-site SwRI employees listed as qualified to perform Level I or II ultrasonic, liquid penetrant, magnetic particle or visual examinations for compliance with SflT-TC-1 A as required by ASME BYPV Code,Section V,1974 Edition with Addenda through Sux.er 1975. The areas of the personnel records observed satisfied the qualification require-ments.
The inspector also reviewed the certification records for all seven on-site CE employees listed as qualified to perform level I, II or III Eddy Current examinations for compliance with Silt-TC-1A as required by ASME B&PV Code,Section V,1974 Edition with Addenda through Summer 1975.
These personnel records also appeared consistent with the requirements.
flo items of noncompliance or deviations were identified.
(3) Observation of Liquid Penetrant Examination The inspector witnessed the liquid penetrant examination of a 12-inch shutdown cooling line pipe restraint weld (Line 12-SDC-2001 Joint 9-PS) per procedure SwRI-fiDT-200-1, Revision 42. flo reportable indications were revealed by the colcr contrast inspection technique.
The inspection materials, technique and personnel for the areas inspected were consistent with the procedure and requirements for liquid penetrant examination of ASME B&PV Code (1974 Edition with Addenda through Summer 1975).
flo items of noncompliance or deviations were identified.
(4) Observation of Ultrasonic Examination The inspector witnessed the calibration and manual ultrasonic examination of a butt weld in a 12-inch low pressure spray injection line, weld 12-LPSI-2002-5, per procedure SwRI-fiDT-600-3, Revision 4.b.
Examination was limited on
..
-
.
-
.
.
.
_g.
the bottom eight inches of the joint due to the config-uration of the valve on the downstream side of the circumferential butt weld.
Reportable indications were found and recorded on the inspection data sheet. The inspection equipment, technique, personnel and calibration for the areas inspected complied with the procedure and Section V and XI requirements of ASME BSPV Code (1974 Edition with Addenda through Summer 1975).
No items of noncompliance or deviations were identified.
(5) Observation of Eddy Current Examination The inspector witnessed the inspection of two tubes (L85-R64 and L86-63) in the "A" steam generator as performed by Combustion Engineering personnel per Procedure 00000-MLE-082-07 and Special Procedure SP-RC-2.
Inspection equipment, personnel and calibration for the areas inspected were in accordance with the procedures and Section V and XI requirements of ASME B&PV Code (1974 Edition with Addenda through Summer 1975).
No items of noncompliance or deviations were identified.
c.
Review of Records
,
The inspector reviewed the SwRI records for documentation of calibration and ultrasonic examination of the Low Pressure Safety Injection pipe weld joint 12-LPSI-2002-5 in accordance with Procedure SwRI-NDT-600-3-R46. No discrepancies were noted in the records which were reviewed.
The data presented in the records was found to meet the requirements of Section V of the ASME B&PV Code.
No items of noncompliance or deviations were identified.
8.
Exit Interview The inspectors met with licensee representatives (denoted in paragraph 1)
on October 27, 1978 and with the Acting Plant Manager on November 3, 1978. At these meetings, the inspectors summarized the scope and find-ings of the inspection.