IR 05000289/1977019
| ML19256D344 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/06/1977 |
| From: | Davis A, Fasano A, Kellogg P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256D338 | List: |
| References | |
| 50-289-77-19, NUDOCS 7910170848 | |
| Download: ML19256D344 (7) | |
Text
- -. - _ _ _..
- - - -
.-
-. - - -
..--...--.u._
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
,o Region I Report No.
77-19 Docket No.
50-289 License No. DPR-50 Priority Category C
--
Licensee:
Metropolitan Edison Company P. O. Box 542 Reading, Pennsylvania i
Facility Name:
Three Mile Island, Unit 1
_
!
Inspection at:
Middletown, Pennsylvania i
Inspection conducted:
June 7-9, 1977 7///77 Inspectors:
/
bo e A.
a o
r Inspector
' dat si ned
l
~M
C $7
,
'q p J.frpiloa tnr nepector
' pa * s'i g'ned
-
%
,
'
date signed f'
f
Approved by:
[I3 7/t./77 W
f. B. Davis, Chief, Reactor Projects 4date signed Section No.1, RO&NS Branch
-
Inspection Summary:
Inscection on June 7-9, 1977 (Report No. 50-289/77-19)
'
Areas Inspected:
Routine, unannounced inspection of plant operations including observations of the can'.rol room and a general plant tour; followup on previously identified Unresolved Items; followup on responses to NRC Bulletins and Circulars; review of Licensee Event Reports.
The inspection involved 42 inspector hours on site by two NRC inspectors.
Results: No Items of Noncompliance were identified.
1454 308 s_.
Rdgion I Form 12 7910170 (Rev. April 77)
-.
-
-
'
-
.
,
I b
DETAILS 1.
Persons Contacted Metropolitan Edison Company Mr. R. Barley, Lead Mechanical Engineer Mr. W. Cotter, Supervisor - Quality Control
- Mr. C. Hartman, Lead Electrical Engineer I
Mr. G. Hitz, Shift Supervisor i
Mr. G. Kunder, Supervisor of Operations l
Mr. L. Noll Shift Foreman
- Mr. J. O'Hanlon, TMI-1, Unit Superintendent
,
Mr. J. Principe, Quality Control Inspector
'
- Mr. M. Shatto, Engineer Associate II, Nuclear Mr. H. Shipman, Operation Engineer II Mr. R. Summers, Engineer Nuclear II
I The inspector also talked with and interviewed 7 other licensee employees during the course of the inspection.
Other Accompanying NRC Personnel n
H. D. Thornburg, Director, Division of Reactor Operation Inspection a
- denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved item 289/77-05-05:
Completion of revision documentation of limitorque adjustment procedurt s.
The inspector j
reviewed procedures 1420 LTQ-1,2 and 3 which hare been revised and have been approved, completing this item.
,
(Closed) Unresolved item 289/77-14-02, OH-V1 Furmanite Chlwide analysis. Two samples of Furmar.ite were given to the NRC for analysis. The first sample was approximately 6 grams, the second about 22 grams. The samples were forwarded to the Idaho Hralth Service Labori. tory (1HSL) for analysis.
The sr.mples were anclyzed for chloride content and for leacha.ble chloride.
The first sample (4 gram) gave results that did not agree with esults obtained from three laboratories doing similar analyses on tie furmanite.
The second sample, 22 grams, was divided among thf s lab (IHSL) and two other laboratories.
The results from this san ple were consistent with the licensee's results. The total chloride is in the order of G
1454 309
--
-.._.. - - -
.-
.'
.
-
.
,
,
O 50 ppm. The leachable chloride is less than 10 ppm.
The most probable explanation of the high chloride results in the 4 gram sample is external contamination between the time of sampling and IHSL's measurement.
The inspector also reviewed the purchase request, order Number 31923 and discussed the method of receipt and handling the nuclear grade furmanite. The furmanite was received on one sheet which was cut into strips about two to three inches in length and about inch wide.
The pieces were kept in plastic bags for protection. A total amount of 390.45 grams was used in the repair of valve DH-V1.
The sample (4 gram) sent to IHSL had previously been sent to a GPU Laboratory,
was held in this laboratory for a period of time and was then repackaged and sent to the NRC where it was forwarded to IHSL. The
second sample was delivered to the NRC inspector from the original bag and immediately sealed in an envelope and forwarded to IHSL.
Discussian with the licensee indicates that he is currently pursuing the purchasing of a suitable replacement valve for Oh-V1.
3.
Plant Operations
'
Shift Logs and Operating Records
,
The Control Room Log Sheet entries for the period May 17 through June 7,1977 were reviewed for completeness.
Parameters recorded in the
'
data sheets were independently checked by the inspector. The comparisons
.
'
were acceptable.
The log sheets were complete with required signatures.
The inspector had no further questions on this item.
,Me.itoring Instrumentation The following instruments were checked against the licensee's recorded data; BWST Temperature
--
Sodium Hydroxide level and temperature
--
Sodium Thiosulfate level and temperature
--
- Reactor Building Pressure
--
Penetration pressure
--
Reactor Coolant Pump Seal leak off flow
--
- RM-A-5, Radiation Monitor, gas
--
The asterisk designates those recordings that were also verified at positions outside the control room.
1454 310
,
,
-
-
-
__
-_
.-
---
.
-
.
l
,
)
'
The readings were within acceptable limits.
Remote readout data agreed with the control room indications.
The inspector observed the activity decrease indicated on the containment radiation monitors due to the purge in progress on June 9, 1977.
Equipment Lockout Tags
!
" Caution, Do Not Operate" tags numbered 636 and 665 were checked with the application for apparatus to be out of service forms.
The field motor, valves and breakers were checked to correspond with the required tags related to the secondary service cooling river pump and found to be in order.
Control Room Alarms The inspector reviewed the status of the panalarm board. The following alarms were on:
Feed water pump-turbine filter, oil conditions
--
Reactor coolant pump seal leak off flow
--
Heat trace trouble
--
O Penetration pressurization system pressure iow
--
480 motor overload
--
j Station battery A ground
--
I The reactor operator was cognizant of the alarms and knew the reasons
-
for the alarms.
!
Tour of Accessible Areas
,
The inspector observed operations in the Control Room and made tours of the Auxiliary, Turbine, and Intermediate Buildings, Diesel Generator Rooms, and Storage Battery Rooms on various occasions during the inspec-tion. Activities observed included the following:
.
Radiation controls properly established
--
Plant housekeeping conditions
--
Existence of fluid leaks
--
Existence of piping vibrations
--
Proper oil levels in snubbers installed in the Building Spray System
--
Valve positions or equipment start switches for the diesel generators
--
and building spray pumps 1454 311
-. -
. -
.-
-
.-.. -.
-
.-
-.
..
-. -
.
-
.
.
)
I
"
Plant tours by the Shift Supervisors
--
Control Room Manning
--
'
No items of noncompliance were identified.
Instances of valve stem and i
leak off incrustation in borated water systems were discussed with the Unit Superintendent.
These items will be reinspected during a subsequent inspection.
(289/77-19-01)
i The inspector noted the diesel generator voltage control rheostat mounted on the local panels was not marked for normal voltage settings.
The inspector discussed this lack of indication with the facility staff.
The licensee indicated a design change to install an additional rheostat i
inside the panel is being investigated. This item will be reinspected i
j during a subsequent inspection.
(289/77-19-02)
4.
Licensee Event Followup a.
The Licensee Event Reports (LER's) listed in subparagraph b. were
reviewed in the Region 1 office promptly following receipt. The
'
purpose of the inoffice review of each LER is to determine whether additional reactive inspection effort or other IE response is warranted, whether corrective action discussed in the LER appears
i appropriate, whether information reported to the NRC satisfies O
reporting requirements and whether the event is appropriate for
!
'
classification as an Abnormal Occurrence,
,
i j
Based on the aforementioned review, the inspector had no further questions on these LER's.
i b.
LER's reviewed.
(1) 77-2/4T River water discharge exceeded the inlet river water temprature by 140 F.
(2) 77-3/3L Reactor Building spray pumps suction isolation valve motor failed.
i
(3) 77-4/lT Nonconservative error used to support increasing the safety valve setpoint.
(4) 77-5/4T Chang? in river water discharge temperature exceeded 20 F in one hour.
(5)
77-6/lT Combined local leak rate test exceeded 0.6 La.
1454 312
.
.em==-
e, op g
.
..-
g
-...
. -. -. - -
_--
.
... _. - -..
~
.
,
.-
.
,
i
1
<
(6) 77-7/lT Both doors of the reactor building emergency personnel access hatch open at same tirca.
(7)
77-8/3L Snubbers failed to perform within acceptance
'
criteria.
(8)
77-9/lT Steam Generator LOCA restraint bolting was found loose.
(9) 77-10/lT Incorrect calculation of core thermal power.
All of the above listed LER's were elected for onsite inspection to determine whether the licensee's review of corrective action and report of the identified event and associated conditions are adequate anJ in conformance with regulatory requirements and technical
,
specifications.
'
This review included physical observations of corrective actions, where appropriate, discussions with members of the plant staff, and inspection of PORC meeting minutes, work requests and surveillance
,
reports.
i
'
No items of noncompliance were identified.
7 3
_a With respect to LER 77-3/3L, 77-4/lT, and 77-7/lT corrective actions were in progress but had not been completed.
These actions will be reviewed during a subsequent inspection.
(289/77-19-03)
5.
IE Bulletins a.
Selected IE 3ulletins were reviewed to verify that:
(1)
information was for.sarded to onsite management; (2)
information discussed in the licensee's reply was supported by facility records, or by visual examination of the facility; (3) corrective action taken was effected as described; and, (4) the reply by the licensee was prompt and within the time period in the bulletin / circular letter considering mail delays.
b.
The IE Bulletin reviewed was:
77-01 Pneumatic time delay relay setpoint drift.
1454 313
'
.
- _. -
-
.. - -._ -.
.
..
.__
__ _
_
_.
._.
_ _ _ _ _ _.. _ - _
.
.
.... -
.
,
!
.
( )
c.
The review included visual observations of equipment, discussion with licensee personnel involved with the review / corrective actions and inspection of records.
No items of noncompliance and no discrepancies with respect to the licensee's responses were identified.
i 6.
IE Circular Followuo
,
!
The inspector reviewed the licensee's followup actions regarding IE l
Circular 77-06, Effects of Hydraulic Fluids on Cables. The inspector determined that this Circular has been reviewed for applicability
by plant engineers and operating staff personnel. The licensee has
,
j initiated appropriate corrective action, as described in the Circular, when applicable.
The inspector had no further questions at this time.
7.
Exit Interview An exit interview was held onsite with licensee representatives (see Paragraph 1 for attendees) to discuss the findings of this inspection.
The licensee acknowledged those items which will receive followup inspection as disclosed in this report.
mU i
1454 314
!
!
,
.-_
,, -
w,g
-
-.
.
--