ML17256A904
| ML17256A904 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/05/1982 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8205110459 | |
| Download: ML17256A904 (6) | |
Text
REGULATORY ORMA'TION DISTRIBUTION SYS (RIDS)
ACCESSION NBR:8205110459 DOC ~ DATE: 82/05/05 NOTARIZED:
NO DOCKET FACIL:50-244 Rober t Emmet Ginna Nuclear PlantP Uni~t ii -Rochester G
05000244 AUTH'AME AUTHOR AFfILIATION MAIERgJ ~ E, Rochester Gas 8 Electr ic Corp0 RBCIP ~ NAME RECIPIENT AFFILIATION
-CRUTCHF IELD P D ~
Operating Reactors Branch '5
SUBJECT:
Submits addi info re revisions to Procedure E
1~4'Steam Generator Tube Rupture
" discussed in incident evaluation rept transmitted in util 820413 ltd DISTRIBUTION CODE:
DOOTS COPIES RECEIVED:LTR J ENCL 0 SIZE:.
TITLE: Ginna (50-244)
Steam Generator Tube Failure NOTES:NRR/DL/SEP icy, 05000244 RECIPIENT ID CODE/NAME ORB 05 BC 01 INTERNAL: IE 05 NRR DIR 12 NRR/DHFS DIR 09 A
11 FI 04 COPIES LTTR ENCl RECIPIENT ID CODE/NAME IE/DEP 13 NRR/DE D IR 08 NRR/DL DIR 07 NRR/DST DIR 10 RGNi 06 COPIES LT!TR ENCL EXTERNAL: ACRS NRC PDR NTIS 14 02 10 1
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ROCHESTER GAS AND ELECTRIC CORPORATION
~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAIBR Vice President TELEPHONE AREA CODE 716 546-2700 May 5, 1982
Subject:
Procedure Revisions Incident Evaluation Steam Generator Tube Rupture Incident R.
E. Ginna Nuclear Power Plant Docket No. 50-244 Director of Nuclear Reactor Regulation Attention:
Mr'. Dennis M. 'Crutchfield, Chi'ef Operating Reactors, Branch No.'"5 U.S. Nuclear Regulatory Commission Washington, D.CD 20555 6'pgg,o go )9N,~
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~gy, W~~@ s ggggl Dear Mr Crutchfield:
In our Incident Evaluation Report, submitted by letter dated April 13,
- 1982, we discussed changes being made in the Ginna Procedure E-l.4, "Steam Generator Tube Rupture".
This letter provides revisions and additional information regarding procedure changes.
1
~
Since a qualified wide range reactor coolant loop pressure transmitter is being installed during the current outage, the loop pressure at which the reactor coolant pumps are to be tripped will be revised.
We expect the trip pressure to be approximately 1200 to 1300 psig.
The exact value will be calculated in accordance with Westing-house Owners Group and NRC guidance-2.
Based on more recent guidance from Westinghouse, STEP 3 '7 is being revised as follows:
"Establish charging and letdown flows to maintain the pressurizer water level between 80% and 90%,
no RCPs
- running, and between 25% to 50%,
RCPs running.
3.
Based on more recent guidance from Westinghouse, the CAUTION after STEP 3.17.1 is being revised as follows:
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((o "If, during subsequent recovery actions, pressurizer water level cannot be maintained above 20% indicated level or subcooling is less than 30oF, manually initiate SIP operation to maintain level in the operating range and subcoo~nt
--~ If pressurizer water level or subcooling egpsg f045 p~pppg44 9 egpsps
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ROCHESTER GAS AND ELECTRIC CORP.
DATE May 5, 1982 TO Mr. Dennis M. Crutchfield SHEET NO-2 cannot be established by this method, manually initiate SI and return to STEP 3.13 and proceed with the instruction from that point ~
4, Based on more recent guidance from Westinghouse, the NOTE after STEP 3.18 is being deleted and, in its place, a
NOTE is being added after the CAUTION discussed in item 3 above as follows:
"A bubble should exist in the pressurizer with indicated level between 80% and 90% before RCP start to compensate for possible RV head bubble collapse."
It is noted that future procedure revisions may result in step renumbering or in wording changes.
- Further, implementation of Revision 3 of the Westinghouse Owners'roup procedure guidelines, following NRC approval, will result in major changes to the pro-cedures.
The intent of the procedure changes described above'nd in our April 13 report will-be maintained through the procedure changes.
Very truly yours, Ja n E. Maier
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