ML20064C326
| ML20064C326 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/10/1978 |
| From: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7810180117 | |
| Download: ML20064C326 (5) | |
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ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCic-AAKANSAS 72203 (501) 371-4422
.10ctober 10, 1978
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WILLIAM CAVANAUGH 111 f
Executive Drector Generaton & Constructen 2-108-2 Director of Nuclear Reactor Regulatory ATTN: Mr. J. F. Stolz, Chief Light Water Reactors Branch #1 U. S. Nuclear Regulatory Comission Washington, D. C.
20555
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Subject:
Arkansas Nuclear One-Unit 2 Docket! No. 50-368)
Licens(e No.JLE-6 Technical Specification Change Request (File:
2-1510.1)
Gentlemen:
Our letters of August 31, 1978, and September 14, 1978, transmitted our interim procedure for post accident radiation monitoring (while we are completing qualification testing of our permanent instruments).
We understand, fromconversations with members of your staff, that this procedure has been accepted. The staff has requested, verbally, that we submit appropriate technical specification changes to reflect this interim procedure. Accordingly, our proposed technical specification change is attached. Our proposed change allows us to utilize the interim i
procedure through July, 1980. This particular date was chosen to assure that the interim procedure could be used until the first refueling outage.
We have determined, in accordance with 10CFR170, that this technical specification change request is defined as a class II change request as it is of no significant safety or environmental consequence. Accordingly, a check for $1,200.00 is enclosed.
Very truly yours,
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William Cavanaugh III WC:JTE:jaj Enclosure 1 tiolt Oll1h MEMOEA MrOOLE SOUTH UTIUTIES SYSTEM
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,. o STATE OF AP/.At:3A3
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SS CCunY OF PUU6Fl
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Willian Cavanaugh III, being dul;y sworn, states that he is Exeer.nive Director, Generation & Construction, for Arkancas Power & Light Company, trat ne is autnorised on the part of said Company to sign and file with tne Naclear liegulatory Comission this Supplemntar/ Infomation; that he nas reviewed or caused to have reviewed all of the statements contained in cucn infon.ntion, and that all such statements made and tratters set forth therein are true and correct to the best of his knowledge, infora-tion and belief.
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William Cavanaugh III
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\\J SUBSCPTRFri NID SdCRI TJ before me, a Notary Public in and fcr the County and State above named, this \\\\ day of CRToust.
197d.
- t. k Iiotary Public dy Cor:raission Expires:
February 17, 19d2
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t TABLE 3.3-10 t
E POST-ACCIDENT IiONITORING ' INSTRUMENTATION i
a M
filHIMUM
+
CHANNELS i
i c-INSTRUMENT OPERABLE
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t 1.
Containment Pressure 2
a i
2.
Containment Radiation Monitors
- 2 3.
Pressurizer Pressure 2
4.
Pressurizer Water Level 2
5.
Steam Generator Pressure 2/ steam generator j
6.
Steam Generator Water level 2/ steam generator 7.
Refueling Water Tank Water Level 2
?
I 8.
Containment Sump Water Level 2
- This requirement may be satisfied (through July 1980) by the use of portable radiation monitors equivalent in number to the minimum
'I channels required to be operable.
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TABLE 4.3-10 g
POST-ACCIDENT M0'lITORING INSTRtEENTATI0ft SUP.VEILLANCE REQUIREMENTS _
G i
i CHANNEL CHANNEL INSTRUMENT.
CHECK CAllBRATION C
i 1.
Containment Pressure 11 R
'2.
Containment Radiation l'onitors*
M R.
3.
Pressurizer Pressure il R
4.
Pressurizer Water level ti R
5.
Steam Generator' Pressure M
R l
l 6.
Steam Generator Wa ter Level M
R 0
w 2
7.
Refueling Water Tank Water Level M
R w
1.
8.
Containment Sump Water Level M
R i
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- This requirement may be satisfied -(through July 1980) by use of portable radiation monitors, and by substituting a source check for the channel check and by substituting an instrument calibration for the channel cclibration.
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