ML18219D817
| ML18219D817 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/01/1978 |
| From: | Dolan J American Electric Power Service Corp |
| To: | Kniel K Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18219D817 (7) | |
Text
e~c-fry ge REGULATORY INF NATION DISTRIBUTION SYSTEM (RID DISTRIBUTION FOR INCOMING MATERIAL 5/-
6 REC:
KNIEL K NRC ORG:
DOLAN J E
IN 8c MI PNR DOCDATE: 06/01/78 DATE RCVD: 06/13/78 DQCTYPE:
LETTER NOTARIZED:
NQ COPIES RECEIVED
SUBJECT:
LTR 1
ENCL 0 FURNISHING INFO SUPPORTING APPLICANT"S BELIEF THAT THE FOXBQRO TRANSMITTERS THAT MEASURE PRESSURIZER PRESSURF AND STEAM GENERATOR STEAM FLOW ON UNIT 2 ARE QUALIFIED FOR STEAM LINE BREAK ACCIDENT CONDITIONS.
PLANT NAME: COOK UNIT 1
COOK UNIT 2 NOTES:
I 5 E 3 CYS ALL MATERIAL REVIEWER INITIAL:
XJM DISTRIBUTER INITIAL:0~
pI
~>>++++++++>++++>+ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS PSAR/FSAR AMDTS AND RELATED CORESPONDENCE (DISTRIBUTION CODE B001)
FOR ACTION:
INTERNAL:
EXTERNAL:
ASST DIR D EISENHUT+>LTR ONLY(i PROJ MGR REEVES++LTR ONLY(1)
G II 4+LTR ONLY< 1)
I 5 E4+LTR ONLY(2>
OPERATOR LIC BR4+LTR ONLY(i)
QAB++LTR ONLY(1)
MIPC++LTR ONLY< l )
MECH ENG BR>4LTR ONLY(l)
MATERIAL ENG BR4+LTR ONLY<2)
REACTOR SYSTEMS BR++LTR ONLY(i>
CQRE PERFORMANCE BRcc4LTR ONLY<i AUXILIARYSYS BR++LTR ONLY(l)
I 8c C SYSTEMS BRcc4LTR ONLY(1)
AD FOR SITE TECH44LTR ONLY(4)
ACCIDENT ANALYSIS+4LTR ONLY(1)
RAD ASSESSMENT BR4+LTR ONLY(i)
LPDR S ST.
JOSEPH'I++LTR ONLY< 1 )
'IC++LTR ONLY(1>
NSIC4+LTR ONLY'<1)
ACRS CAT B++LTR ONLY(ib>
BR CHIEF ORBOi BC++LTR ONLY(i>
LIC ASST'RBWi LA+4LTR ONLY(1)
NRC PDR4.+LTR ONLY< 1)
OELD++LTR ONLY(i>
EMERGENCY PLAN BR++LTR ONLY<i)
CASE+4LTR ONLY(i>
AD FOR ENG++LTR ONLY<i)
STRUCTURAL ENG BR4>LTR ONLY(i)
ANALYSIS BR4<LTR ONLY(i>
AD FOR PLANT SYSTEMS~<LTR ONLY<
CONTAINMENT SYSTEMS>+LTR ONLY(f POWER SYS BR+<LTR ONLY< 1)
AD FOR SITE ANLYS>+LTR ONLY(1)
EFFLUENT TREAT SYS<+LTR ONLY<i)
KIRKWOQD++LTR ONLY(i >
DISTRIBUTION".
LTR 56 ENCL 0 SIZE:
3P CONTROL NBR:
7816500b3 THE END NM%%%%%%4 <<c 44%%%%%4%%%%%%0%%%%%%%%0
NRC 3031305 006
, FILE'EVEI S
. DOC.
DATE UNITED STATES NUCLEAR REGULATORY COMMI'DC DAILY Af'CESSION LIST 05/04/78 a
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Pt.IUITORE 9i+ui8 B5 5lP'l, AMERICAN ELECTRIC POWER Service Corporation 2 Broadfoay, Neo York, N. Y. JOOOci (2l2) 422 -4800 JOHN E.DOLAN Senior Encennec Fiec Pfccuknc Esginecfing
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Mr. Karl Kaiel, Chief Light Water Reactors Branch No.
2 9
Division of Project Managemen 4
United States Nuclear Regulatory Commission Washington, D. C.
20555 June 1,
1978 AEP:
Dear Mr. Kniel:
Per your request, this will transmit to you a record of our conference call on June 1 with regard to our program for qualifying transmitters on Donald C.
Cook Nuclear Plant Units 1 and 2.
This conference call involved Messrs.
R.
W. Jurgensen and J.
C. Jeffrey and myself at AEP and Messrs.
R. Tedesco, T. Ippilito, C. Miller, R. Cudlin and yourself at NRC.
At the March 20, 1978 meeting with the Commission, we presented data to support our belief that, the Foxboro transmitters that measure pressurizer pressure and steam generator steam flow on Cook Unit 2 were qualified for steam line break accident condi-tions.
We still believe those arguments are valid and that they provide adequate assurance that operation of Cook Unit.
2 does not involve undue risk to the public health and safety.
Understanding,
- however, that, the.NRC has some reservations as to the arguments we presented, we have 'established the follow-ing programs that we believe will remove all such reservations.
ROSEMOUNT TRANSMITTERS On March 28, 1978 we verbally ordered a total of 30 transmitters from Rosemountc Incorporated.
The order involved 16 steam generator steam flow transmitters plus 4 spares to cover both Units 1 and 2. It also included 8 pressurizer pressure trans-mitters plus 2 spares, also for both Units 1 and 2.
Delivery of all 30 transmitters is expected in September October of this year.
~ ~
I'
Mr. Karl Kniel 6/1/78 Although your questions formally only relate to Unit 2, we believe it is prudent to treat both units equally.
As to the qualifications of the Rosemount transmitters, 3
differential transmitters have each been sequentially tested to meet IEEE 344-1971 and IEEE 323-1971, irradiated to 44
- megarads, then seismically tested, then environmentally tested to conditions that more than envelope our steam line break accident conditions.
We have the Rosemount report on such tests and we are reviewing it for our concurrence with Rosemount's statement that the transmitters passed the tests successfully.
We are further checking the acceptance criteria for output signal accuracy and evaluating the results against the Westinghouse accident analysis.
The output signal of the tested transmitters is 4-20 ma whereas our'circuits require 10-50 ma.
We have developed circuit changes that willaccommodate this difference and are checking these with Westinghouse.
Any change will be com-pletely external of the transmitters and, therefore, not affect the test results.
al While only differential transmitters were sequentially tested, we believe that the pressure transmitters are equally qualified since they are identical in des'ign and installation except that one sensing line will be unconnected.
To further confirm this
- belief, an individual environmental test was run on a pressure transmitter.
BARTON TRANSMITTERS As you know, we replaced 12 steam generator level, 3 pressurizer
- level, and 2 reactor coolant pressure transmitters on Cook Unit 2 with new Barton transmitters prior to startup.
Full sequential qualification testing on such Barton transmitters is underway at Westinghouse and expected to be physically completed by the end of July 1978.
We placed an additional order with Westinghouse on March 23, 1978 for similar Barton transmitters to be installed on Unit l.
Westinghouse has ordered a second lot of Barton transmitters which will include those
'we have 'ordered for Unit l.
Yesterday I received notice from Westinghouse of their ability to advance delivery toward March '1979.
Westinghouse believes'hat the qualification test on lot one will be applicable to lot two, but they still intend to do verification testing on additional samples from lot two.
I mentioned on the phone that while we expect the Rosemounts to be fully qualified, we are examining the merits of ordering additional Barton transmitters as a further backup to the
Mr. Karl Kniel 6/1/78 Rosemounts on the pressurizer pressure and steam generator steam flow applications.
~summar We believe thi.'s brief outline 'of our program on transmitters answers your tel'ephone request of'ay. 31 to Mr. R.
W.
Jurgensen'.
Based on what has bee'n outlined, we expect to re-place the'pecified Foxboro transmitters on both Cook Units 1 and 2 not later than the'ext refueling outage of each unit currently contemplated for April 1979 on Unit. 1 and October November 1979 on Unit 2.
We will earnestly examine opportunities for earlier installations following receipt and qualification of the individual transmitters.
We further believe that, based on the presentations made to you at past meetings, the continued operation of Cook Unit 2 prior to replacement of the'pecified Foxboro transmitters does not create any undue hazards to the'ub'lic health 'and safety.
Very truly yours, Senior ohn E. Dolan xecutive Vice President Engineering American Electric Power Service Corporation JED:rm
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