ML20084F634
| ML20084F634 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/23/1973 |
| From: | Platt C ROCHESTER GAS & ELECTRIC CORP. |
| To: | Oreilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20084F607 | List: |
| References | |
| AO-50-244-73-09, AO-50-244-73-10, AO-50-244-73-9, NUDOCS 8304210200 | |
| Download: ML20084F634 (5) | |
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' \\$y ROCHE5TCR gas AND ELECTRIC CORPORAil0N e 89 CA57 AVENUE, ROCllESTER, N.Y.18649
..e um.a :.n nto October 23, 1973 Mr. James P. O'Reilly, Director Dhectorate of Regulatory Operations Reaf on I U.'S. Atomic Energy Commf asion 631 i' ark Awenue King of Prussia, Pennsylvania 19406
Subject:
Abn(sma OccurrenceE:
' 73-9
,cessive Cooldown Rate
'3-10 Malfunction of Safety Injection Pump Suction Transfer from Boric Acid Storage Tanks to Refueling Water Storage Tank R. E, Ginna Nuclear Power Plant, Unit No.1
Dear Mr,
O'Reilly:
In accordance with Technical Specification Section G.6.2a, Abnormal Occurrence Reports, which requires notification by telephone and telecroph, the following icporte oro submitted.
Abnormal Occurrenco 73 Reactor Coolant Cooldown Pate in execss of Technical Specification limits.
I.oss of outsido power to Ginna Station occurred on October 21,1973 at I
appro:timately 0552 hours0.00639 days <br />0.153 hours <br />9.126984e-4 weeks <br />2.10036e-4 months <br /> resulting in a reactor trip.
It is theorized thht an electrical disturbance on the instrument busses within th: plant was created during tlie loss of power. This disturbance caused the overpower delta temperature reactor trip signal to trip the reactor. The loss of outsido power also generated a turbino trip algnal.
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gDRADOCK 05000244 PDR Disturbances on the instrument buses or the ensuing loss of two of four instrument buses due to the loss of outside power also generated a " low low steam generator 1cvel" condition in both steam generators.
One result of this
M T%,2 porttF57in cht AND CLECTRic CORP.
- pryr C/ctober 23, 1973 O O
Co Mr. J, p, O'Reilly signal is the automatic start of the steam driven auxiliar/ eedwster pump.
f ihc di: charge valver to this purnp are normally in the open position.
The automatic start of this pump rosulted in ambient temperature water from the condencate storage tanks being pumped into the steam generators. The cold wister injected into the steam generators cooled down the reactor coolant system to the point that the safety injection signal was generated by a com-bination of low pressurizer pressure and lovel.
Investigation into the cooldown rate as indicated by the strip chart recorders revealed that the cooldown rute ac defined in the Technical Specifications, Section 3.1.2.1 Cooldown Itc m h,, may have been exceeded, Tne cooldown rate is difficult to determine av[urately due to the loss of instrument busses which disabled various indicators and recorders for a short period of time.
Reconstruction of the inic<mation on the recorders when power was restored 0
indicated that the change in temperaturo was approximately 85 T in opprox!-
mately 10 minutos. Tnic is in excoca of the 100 P/hr. limit and is report-able en on abnornuil occurrence as defined in Section 1.9b, " Violation of a limiting condition for operation established in the Technical Specifications."
The PORC met ard discussed the problem. Westinghouse was contacted to determine what possible deleterious effect the repid cooldown could have had on the reactor vessel. Their initial analysic and comr.aricon with similar instancos et othur facilitida indicate stress levels to be acceptable and the effect of this one cooldown cycle to be insignificant in the allowable fatigue life of the vessel,
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ry.tr Octolwr 23, 1973 to Mr.J. P. O$ollly Abnormal OcqtrI,e.nca 73-10_- Malfunction of Safety Injection Pump Suction.
transfor from Boric Acid Storagu Tanks to Refueling Water Tank.
After the lost of outcido power and subsequent initiation of the safety injection signal, the transfer of the safety injection pumps suction fro:n the Boric Acid Storage Tanks to the refueling water storage tank may have occurred prematurely.
The set point is such that the transfer should occur at 10% level in the Boric
, Acid Storage Tanks in conjunction with a sofoty injection signal. It is believed that the transfer occurred at approximately 50% level, Chemistry analysis and volumo inventory analysis indicates that no more than 700 gallons of 12% Boric Acid was delivered to the reactor coolant system. The cause for the malfunction h.:sc not been determined at this time. This incident is reportchle as an abnorrnal occurrence as' defined in the Technical Specification Section 1.9d, "Tailure of one or more components of an engineered safety feature or plant protection system that causes or threatens to cause the feature or system to be incapable of performing its intended function."-
The IDP.O mot Snd discussed the problem. Invoetigation (S Continuing to determInc the CSUSO.
i The station is being m'aintained in the hot shutdown condition. Work is in progress to:
- 1. Investigato the reason for the init!611030 of Olectrical power and disturbancos on the instrument bussos.
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- 2. Investigate the cause ci the premature closing of the 11oric Acid l
Storago Tank Valvas.
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pg U
V I f, Air. October 23, 1973
' ro Mr. J. P, O'lleilly In addition, the following work is being accomplished:
1.
Chant 2e instrutnent and control setpoints for 2000 psia operation, 2.
Inctallation of additional pressure taps on main steam line in connection with continuing investigation of pipo vibration.
3.
Conduct other station maintenance.
Ver/ truly yours, Charles E. Platt, Superintendent Ginna Station xc: Mr. John F. O'I.eary O
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Form AFC-94 (Rev. M ay 14. 8941) AILM C243 Nota and return.
For signatuM.
Ftr lafarm atloa.
To,LMLrE4 8.nd &#it)
INiil CEM1RXS Licensas: Rochecter Gts Mectric Corporation mit Docket No.:
50-244 i!. D. Thornburg, Chief, FSSEB Abnomal Occurrence: A0 73-9 & A0-43-10 To (N2me sad e.mt)
. 44TIALS PLM ARKS RO:HQ (5)
DR Central Files (1)
The attached report from the subject licensee is art Regulatory Standards
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Dir. of Licensing (131 for.:crded in accordance with RO Manual Chanter 1000.
10 (Name and uMt) 2.silALS REMARKS
.R0 Files /
The action taken by the licensee is considered
.O mrt appropriate.
Followup will be performed during the next inspection as appropriate.
copies of 1
FRoM (Name and umt)
REMARES 1
M lbk8' the report have been forwarded to the PDR, Local
-Rgactor Inspector, PWR Section licensee will submit a 10 day written report to cuant no.
I mv5 l
l10/26/73 Licensing.
LI5t OTHER $4L FOR ADDITION AL MMARKS cro ; ists o. esb-44 5
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