ML19220A883
| ML19220A883 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/12/1978 |
| From: | Stair J Metropolitan Edison Co |
| To: | NRC Office of Inspection & Enforcement (IE Region I) |
| Shared Package | |
| ML19220A880 | List: |
| References | |
| MOR-780331, NUDOCS 7904250061 | |
| Download: ML19220A883 (4) | |
Text
Enclosure GQl, OC l T
Docket No.
50-320 UNIT S!!UTDOWNS AND POWEli HEDUCTIONS
-2 Unit Name i
RFTORT MONTil Marc h D a t.e April 12, 1978.
J.
11. Stair Completed By Telephone 21'>-929-30)1 Ext. 118 v
l $7 f
li System Component Cause and Corrective No.
Date Type m
U" S
U wn e@
Code 34 Code 5 Action to e$
m ch om d
Prevent Recurrence 33 wg 7,,o g, sg S *$ U ESf
$$N 0 N v:
1 3/29/78 F
57. f2 A
3 78-21/3L Im a or power monitor to l<cla-1A cauulng HpS to believe no pumps running in one loop.
4 C
C.:.
G Ut O
O P
w I
- l M
I F; Forced 2 Reason; 3
" xhibit G - Instructions 1
M a od 3: Scheduled A-Equipment Failure (Explain)
"E #"
14fanu al g
li-Maintenance or Test Entry Sheets for Licensee 2
"E C-Herueling 3At at i
ma.
D-Itegulatory ttestriction 1 -Other (Explain) 4 E-Operator Training & Licensee Examination F-Administrative S
G-Operational Error (F.xplain)
Exhibit. 1 - Same Source Il-Other (Explain) 6
CPERATING DATA REPCRT Occket No.
50-323
"*-^3 Date
^F M-Cenpleted By J '. St
- CPERATING STAT ~3 Telephcne :::_c^c : R 1 I n. l~
1.
Unit Name: ~hree Mile Island. Unit 2
- 1703 G; 2.
Repcrting Period:
3 Licensed ~her=al Pover (!Gt):
e-' 2 h.
Nameplate Rating (Gress.Y4e):
c61 5.
resign Electrical Rating (Net T4e):
906 6.
Max. Dependable Capacity (Gress Tie): E 7.
Max. Cependable Capacity (Net M'4e):
3.
If Changes Cecur in Capacity Ratings (Items No. 3 thrcugh 7) Since Last Repert, Give Reasons:
N/A 9
Pever Level to which Restricted. If Any (Net M'Je):
- 7/1
- ", a 10.
Reasons fer Restrictions, If Any:
11. Ecurs in Reporting Period
__' d
'S 12.
No. of Hours Reactor was Critical 2/A N/A N/A 13.
Reactor Recerve Shutdevn Hours 1h.
Hours Generater On-Line 15 Unit Reserve Shutdevn Ecurs
- 16. Gross Thermal Energy Generated (!GE) 17 Gross Elect. Energy Generated (M'a'4)
- 13. Net Electrical Energy Generated (!GH) 19 Unit Service Facter 0
o a
20.
Unit Availability Facter 0
3 S
21.
Unit Capacity Facter (Using MDC Net) 0 0
0 22.
Unit Capacity Factor (Using DER Net)
^
n e
23.
Unit Forced Cutage T. ate 0
0 0
2h.
Shutdovns Scheduled Cver Next 6 Menths (?fpe, Date, and Duraticn of Zach):
____ '! ! 1 25 If Shut Devn at End of Report Period, Istimated Date of Startup:
April
, ic-26.
Units In Test Status (Frict to Cc==ercial Operation):
FORECAST ACHIr7ED INITIAL CRITICALI'~Y 7_
c_~a e_ec -:
.,h-.+1, :r
~.-2..--.v.
- _ a_
a_..
t.
CCMERCIAL ORERATICN
- _ c_-a
,..g- ' I O Q
AVIRAGE DAI',Y CTIT PC'4ER '. EVIL Dcchet No.
5C-320 L,,,.<..
. <. 0 Date April 12, 19~3 Cc:pleted By J. F. Stair
'. e.' *',.hc.e f 9'
- W 0 '_ 6, W......
~'*
v.
i.T..m..r.
..a-yie t
DAY A7ERAGE OAILY FC'4ER LEVEL s DAY NIERAGE DAILY FC'4E3 LEVIL*
(M'ie-Net )
(M'4e-Net )
1 3
17 a
2
-10 18 o
_2 3
_ ~. ~ _
h
-3 20
'c 5
-7 21
-?L 6
-7 22
-22 7
-3 23
'O A
-3 2k
?<
o 7
25
-1~
10
-3 26
-lo 11
-15 27
-2~
12
-19 28
-2~
. -)
9 c
-c.
.h
_a 2.0
_ ~ -
e
.E
-17 1.'
's 16
-3
- 2e negati.e ::=bers * " e tha: scre ener g -23 su;Pli-d te the uni: than Fr duced by it and are pre rided f:r ycur inferrati:n :Cy.
t'1 2co t.
SUMMARY
OF CPERATING EXPERIENCE The reactor achieved initial criticality at C437 on March 23, 1978.
The reactor tripped on March 29, 1978. During ES testing of I channel and 1 group of reactor building isolation and cooling, the alternate pcwer supply to 2-lV Vital Bus tripped. Due to a blown fuse, the "A" inverter feeding 2-lV Vital Bus also tripped. This caused a total loss of the 2-lV Vital Bus.
In that we were in a 3 out of 4 Reactor Coolant ump combination and the RC-PI A monitor is fed from 2-lV Vital Bus, the reactor tripped due to sensing a 0-2 Reactor Coolant Pump ccabination.
Also, on the loss of 2-IV Vital Bus the electromatic relief valve failed in the open posi tion.
In approximately 2 minutes the plant blew down to less than 1600#. The pressure bicwdown was ccmoounded by the loss of one-half of the Control Room Nuclear Instrumentation, which is fed fecm 2-lV Vital Bus. Safety Injection initiated at 16004 and the plant continued depressurizing to 11004. Approx-imately 5 minutes into the transient the alternate pcwer supply to 2-lV Vital Bus was reenergi:ed..hich caused the electrcmagnetic relief valve to shut which stopped the plant depressurization.
As a result of Safety Injection borated water from the Borated Water Storage Tank and Sodium Hydroxide from the Sodium Hydroxide Tank were injected into the Reactor Coolant System (RCS). T1e highest sodium concentration seen in the RCS was 430 ppm. The RCS was placed on cleanup by using the Letdown Demineralizers.
While cleaning up the RCS it was deternined that the chloride concentration in the RCS was at 2.3 ppm which was outside of the transient limit.
The chicride contamination was determined to have come from the Sodium Hydroxide Tank. However, the chloride concentration was within the specification limits for the Sodium Hydroxide Tank. A cooldown was commenced in accordance with the Technical Specifications.
Both sodium and chlorides continued to be cleaned up by use of the Letdown Demin-eralizer. Both sodium and chloride concentrations were returned to within ap-propriate limits. An engineering evaluation was performed to assess the chloride impact on the structural integrity of the RCS prior to heatup. On March 31, 1978, the cleai.ap was still in progress.
SAFETY RELATED MAINTENANCE On March 13, 1978 the RC-P2A clutch assembly failed and was removed for inspection and repair / replacement.
On March 15, 1978 due to a potential loose part in the OTSG - part of the Special Inscrumentation Package - the plant was cooled down and 'recairs were made.
71#C1
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