ML19246A584
| ML19246A584 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 05/17/1979 |
| From: | Reed C COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| FOIA-79-98 NUDOCS 7907050004 | |
| Download: ML19246A584 (3) | |
Text
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Commonwealth Edison One F,rst National Ptare. Chc.ago libros e
X Accrets Aeply to: Post Office Box 767
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<ncago. Ines 60690
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May 17, 1979 4
Mr. James G. Keppler, Director Directorate of Inspection and Enforcement - Region III U.S. Nuclear Regulatory Ccr:: mission
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799 Roosevelt Road Glen Ellyn, Illinois 60137
Subject:
Zion Station Units 1 and 2 Additional Response to IE Bulletin No.79-06A (Revision No. 1) dated April 18, 1979 NRC Docket Nos. 50-295 and 50-304 References (a):
April 18, 1979 letter frcru J. G.
Keppler to Byron Lee, Jr. transmitting IE Bulletin No.79-06A (Revision No. 1)
(b):
April 27, 1979 letter from Cordell Reed to J. G. Keppler responding ';o IE Bulletin No.79-06A (Revision No. 1)
Dear Mr. Keppler:
Per Item 13 of Reference (a), Cc~aonwealth Edison Company was requested to subsit technical specification changes resulting from its review of the Three Mile Island Incident.
On April 30, 19'.3 a technical specification change was subnitted (See April 30, 1979 letter frcrn C. Reed to H. R. Denton) to require actuation of safety injection based on 2 cut of 3 channels of low pressurirer pressure, thus deleting precsurirer level from the safeguards logic.
This request was reviewed, evaluated and approved by the NRC Staff on May 3, 1979 as Amendment Nos. 49 and 46 to the Zion Station Units 1 and 2 Operating Licenses (see May 3, 1979 letter from A. Schwencer to C. Reed).
At this time, C m onwealth Edison's reviews have not identified the need for any other technical specification changes.
However, should additional requirements be identified frcm Com=onwealth Edison's continuing review of the Three Mile Island Incident, such changes will be evaluated and subnitted at that time.
G58313 I 0 1979 CC I 79 7050 0
Commonwealth Edison NRC Decket Nos. 50-295/304 Mr. James _G.
Keppler: May 17, 1979 Per Reference (b), Commonwealth Edison indicated that two items, Items 4 and 12, were undergoing further review. to this letter provides an update of these items.
Please address any questions that you might have concerning this matter to this office.
Very truly yours, C.
na Cordell Reed Assistant Vice-President attachment cc:
Director, Division of Reactor Operations Inspection bbM314 e
Commonwealth Edison NRC Docket Nos. 50-295/304
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ATTACHMENT 1 I_ ten 4_
The following valves have been identified as having control switches which allow them to return to their pre-accident position after the safety injection signal is resets s.*
Steam Generator Blowdown FCV-BD17 AOV-BD0001 thru 8 Steam Generator Blowdown Fire Protection FC7-FP08 Instrument Air FCV-IAOlA, B AOV-RV0001 thru 4 Containment Purge FCV-RVlll thru 114 Heating Water Steam Generator Blowdown Sample FCV-SS-2 thru 5 Containment Sump Pump Discharge FCV-WD17A, B FCV-IA01A, B With the exception of valves FCV-FP08, u.d FCV-RVill thru 114, modifications will be initiated to change the control circuits of all the other valves such that they remian
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The valves closed following reset of the safety injection signal.
neppted above serve systems within the containment that are not connected to the reactor coolant system or the containment atmosphere (closed systems) and that have fluid pressure'in excess of accident pressure.
Item 12_
The hydrogen recombiner units are to be used to remove hydrogen from the containment that is generated during a major be Shielding design and requirements will transient.
terms applicable to the Zion units pursued after the source be are identified.
Any other modifications or changes will implemented after applicable requirements became known.
As explained previously in Reference (b), the hydrogen purge fans will only be used to cope with events in which the activity is analyued and the concentrations are kncvn containment to be within the iodine removal capability of the charcoal filters.
Furthernre, the system will nou be used if any releases are calculated to exceed NRC approved limits as defined in Zion's FSAR and Technical Specifications for postulated accidents.
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GbM315
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