IR 05000320/1978015
| ML19220B206 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/20/1978 |
| From: | Coleman W, Haverkamp D, Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220B199 | List: |
| References | |
| 50-320-78-15, NUDOCS 7904250508 | |
| Download: ML19220B206 (7) | |
Text
.
.
_
.
,
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I
_
Report No. 50-320/78-15
.
Docket No. 50-320 Category B-2 License No. DPR-73 Priority
--
Licensee:
Metrocolitan Edison Comoany P. 0. Box 542 Reading, Pennsylvania 19603 Facility Name:
Three Mile Island Nuclear Station, Unit 2 Inspection at:
Middletown, Pennsylvania Inspection conducted: Ma h 30-31 and April 5-6, 1978 Inspectors:
/
- /2o/ / 8
-
D. R. Ha erkamp, ReacSr Inspector ( April 5-6)
date signed
%
iDit 9l20!)V
,
W/E.Co (dn, Reactor Inspector (March 31)
date sioned MA,
'/!20
$
t-Foi g, Reacitor Inspector (March 30-31)
date' signed
<
e Approved by:
.qo['76 D. M. Sternberg, Actnig Chief, Reactor
/date' signed Projects, Section No. 1, RO&NS Branch Inscection Summary:
Inspection on March 30-31 and April 5-6, 1978 (Recort No. 50-320/78-15)
Areas Insoected:
Routine: unar.nounced inspection of licensee's action on previous inspection findings; license conditions for Mode I Operation; and licensee actions concerning an ECCS actuation and infection into the RCS on March 29, 1978.
The inspection involved 38 inspector-hours onsite by three NRC inspectors.
Resul ts:
No items of noncompliance were identified.
(
-
" ' ~ ~ - -, _.,, _
7@YN i
Region I Fom 12 (Rev. April 77)
7 9 0 4 2 5 f) 5og
-
- ee
--
.
.
.
..
DETAILS _
1.
Persons Contacted _
~
Metrocolitan Edison Comoany Mr. P. Lydon, Shift Foreman
- Mr. J. Floyd, Supervisor of Operations
- /**Mr. J. Seelinger, Unit Superintendent - Technical Support General Public Utilities Service Corocration
- Mr. S. Levin, Site Project Engineer Mr. I. Porter, Lead Instrument Engineer
- Mr. R. Toole, Test Superintendent Mr. J. Ulrich, Shift Test Engineer Catalytic, Inc.
'
Mr. J. Webb, Piping Supervisor Pittsburch Testina Laboratory Mr. N. Ritze, QC Inspector The inspectors also talked with several other employees of t.he licensee and the constructor.
31, 1978.
- denotes those present at the exit interviews on March
- denctes those present at the final exit interview on April 6, 1978.
..
Licensee Action on Previous Insoection Findinas (Closed) Unresolved Item 320/77-32-03: Diesel Generator Starting.
The diesel generator air starting system modification has been completed, and the diesels have been started 10 times without (Additional infomation recharging frem the air compressors.
concerning this item is contained in Paragrs" 3.b.)
L
-
i 74 C24
.. q
.
.
.
,
-
-
(Closed) Inspector Followup Item 320/77-42-03:
Approval of TP 600/29.
The inspector detennined that the 1/8 inch and 7/8 inch shims for RC-P-IA Restraint No.10 had been interchanged in accordance with Catalytic Work Authorization Notice No. 546.
QC Inspection Report No. CM-557 indicated satisfactory disposition of this item.
TP 600/29 was subsequently final approved for Mode I operation with no out-standing test de.*iciencies/ exceptions.
(Closed) Inspector Followup Item 320/78-11-01:
Voltage Level Optimiza-tion. A bus voltage measurement test program has been completed and existing transformer tap settings have been verified to be correct.
(Additional information concerning this item is contained in Paragrapt 3.a)
(Closed) Inspector Followup Item 320/78-11-02:
ICCW Heat Exchangers Modification.
Coolers IC-C-IA and IC-C-IB have been modified so that their design conforms with seismic Category I requirements.
( Additional information concerning this item is contained in Paragraph 3.c.)
(Closed) Unresolved Item 320/78-12-02:
Structura! Support Anchorage for Core Flood Tank CF-T-IB.
The inspector reviewed Engineering Devia-tion Report (EDR) No. 4704 for modification of the subject anchor plate and observed the work in progress. The inspector also reviewed Burns & Roe, Inc. letter to GPU, serial 4178-GP, which stated that Burns & Roe has verified that:
_
(1) The plate stress after modification per EDR No. 4704 is within the allowable; and (2) Cut-off of wall reinforcement will not affect the structural integrity of the shield wall.
The inspector subsequently reviewed QC Inspection Reports CS-131 and
~
CS-132 associated with the completed EDR No. 4704, and had no further questions concerning this item.
(Closed) Inspector Followup Item 320/78-13-02:
Housekeeping Conditions.-
The inspector toured accessible plant areas on April 6,1978, and noted that general cleanup activities were continuing, and that housekeeping conditions in the Control Building and Auxiliary Building had improved since the last inspection. The inspector determined that cleanliness and fire protection controls were adequate for entering Mcde I.
~
"f4 CEU i
.
-
-
-
3.
Review of Facility Ooeratinc License DPR-73 Conditions fer Mode I
.
Operation The items discussed below were reviewed for resolution of outstanding conditions of the operating license.
Voltace Level Ootimization of Safety-Related Buses c.
References:
(1)
Burns & Roe, Inc. letter to GPU, arial 4173-GP, dated March 29, 1978; (2) MEC letter to ilRR, serial GQL 0569, dated March 30, 1978.
A bus voltage measurement test program was conducted on March 28, 1978, as described in reference (1). Voltage and current measurements were taken on various safety-related buses while observing operating loads on these buses.
These measurements were converted w arrive at the actual KVA load for each bus.
A compute program was prepared which recreated the plant conditions during the test, and a computer printrut was obtained which listed the expected bus voltage values for the same ter.t program conditions.
Field data was then compared with the analytical results, and the values were within 2.1% agreement, thus establishing a level of confidence in the ability of the analytical program to predict bus voltage behavior during different plant conditions. Analytical values of full load and no load bus voltages were obtained, and it was detemined that in order to optimize voltages at various buses, transformer taps of all Unit Substation buses must be set at -2.5%, as currently exists.
Reference (2) fomarded a report which provided the documntation and confimation of correct voltage tap settings. The inspector reviewed the test methodology and results and referenced reports and had no further questions concerning this license condition.
b.
Diesel Generator Air Startino System Modification During previous testing of the diesel generators, the compressed air starting system had failed to maintain the required minimum air pressure.
Burns & Roe Engineering Change Memo (ECM) No.
5-5866, Rev.1, provided for modification of the system to correct this test deficiency. The inspector reviewed the ECM documentation, observed work in progress on the required mdi-fications, and subs 2quently reviewed the records of satisfactory seismic qualification testing of the added air starting system
'
regulating valves. Additionally, the inspectur detemir.ed
_
,
9I IE l
- .
_._
_
,
-
.
that each diesel generator was demonstrated capable of providing 10 starts without recharging from the air compressors, as documented by the final. approved TP 401/1.
Findings were acceptable regarding this license condition.
c.
ICCW Heat Exchangers Modification Modification of the supports for the Interrediate Closed Cooling Water Heat Exchangers, IC-C-1A and IC-C-IB, was necessary so that their design conforms with seismic Category I requirements.
The inspector reviewed the applicable work authorization notice, nuclear safety review, and QC inspection report associated with the following Engineering Change Memos:
(1) ECM No. 5-5837 for the modifications required to the supports for IC-C-IA.
(2)
2CM's No. 5-5832 and 5879 for the inspection and modification of supports for IC-C-IB.
(3)
ECM No. 5850 for removal of grout above the level of the sliding base p' ate for IC-C-IB.
Additionally, the inspector reviewed Burns & Roe, Inc. letter to GPU, serial 4171-GP, which stated that a seismic analysis was completed to qualify coolers IC-C-IA and IC-C-1B to seismic I loading conditions, and that upon completion of the above ECM's, the coolers and attachments were considered to be Seismic I qualified.
The inspector determined that modifications to the tooler supports had been properly completed in accordance with ECM's S-5832, S-5837, 5850 and 5879, and had no further questions concerning this license condition.
4.
Emergency Safeauards Actuation The inspector reviewed the emergency safeguards (ES) actuation which occurred on March 29, 1978.
The event occurred during the
. perfomance of a monthly ES surveillance test.
During the surveillance test, the circuit breaker for the alternate power supply to the 2-IV Bus was tripped (in accordance with the procedure) and a fuse blew in the inverter which is the primary power supply to the 2-IV Bus.
The loss of power caused the reactor to trip and also opened the pressurizer electromatic relief valve..The relief valve caused (
[
~
l
.
.
-
-
reactor coolant system pressure to decrease to the ES actuation pressure and water was injected into the reactor coolant system.
The event terminated when the fuse was replaced in the inverter.
As a result of the ES actuation, high concentrations of Sodium (Na+) and of Chloride (Cl-) were injected into the reactor coolant system. The licensee commenced a plant cooldown when the measured RCS chloride concentration was discovered to be 2.55 ppm on March 3 '). 1978.
Subsequent to the ES actuation, the RCS was determined to have had maximum assumed concentrations of 4.0 ppm chloride,10 ppb oxygen, and 430 ppm sodium.
B&W letter to GPU/MEC, serial SOM-II-127, dated April 4,1978, stated that the contamination of the RCS will have no deleterious effect upon the stry.tural integrity of the RCS or associated auxiliary systems and equipment.
Therefore, the RCS remains acceptable for continued operation.
The RCS chemistry was returned to within specification on April 4, 1978, and a plant heatup was commenced to resume low power physics testing.
During discussions with licensee representatives, the inspector determined that two modifications are currently being considered to prevent recurrence of tnis event.
A circuitry change is planned to keep the alternate power supply connected to each vital bus in the event of ES channel actuation, and lighted control board position indications will be provided for the electroratic relief valve.
The inspector reviewed the event to verify that the ES system per-formd as desigred, that the licensee was confonning to Technical Specification requirements, that the licensee reviewed the incident for generic imolications, that the licensee reviewed the event for reportability in accordance with Technical specifications and Reg.
Guide 1.16, and that the licensee's plans for restoration of reactor coolant chemistry were consistent with Technical Specifications and vendor requirements.
A scecial report of the ES actuation will be submitted-by the licensee pursuant to T.S. 3.5.2.
The inspector had no further questiens concerning this item at this time.
Find-ings were acceptable.
(
'lb ~
N g
!
!
.
.
,
-
.
.
.
5, Exit Interview The inspector met with licensee and contractor representatives (denoted in Paragraph 1) on March 31, and April 6,1978, to discuss the findings of the inspection.
.
=
-
i
/ 4 C'29
{
..
.