ML19326B830
| ML19326B830 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/17/1975 |
| From: | Phillips J ARKANSAS POWER & LIGHT CO. |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19326B831 | List: |
| References | |
| 742, NUDOCS 8004180575 | |
| Download: ML19326B830 (7) | |
Text
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-' lON FOR PART 50 DOCKET MATER. L AEC DISTRit
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(TEMPORARY FORM) 742 CONTROL NO.
FILE:
FROM: Arkansas Power & Light Co DATE OF DOC DATE REC'D LTR TWX RPT OTHER f
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l-17-75 1-23-75 xxx h
i n TO:
ORIG CC OTHER SENT AEC PDR xxxx Mr. A. Giambusso 1-signed SENT LOCAL PDR
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CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
xxxx 40 50-313 DESCRIPTION:
ENCLOSURES:
Ltr notarized 1-17-75 trans the following:
Proposed Techinical Specifications Changes to the Reactoc Protectior System per AEC approval......
PLANT NAME: Arkansas #1 FOR ACTION /lNFORMATION N -D AB BUT LER (L)
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SALTZMAN UNTZING/ STAFF KNIGHT KASTNER E. GOULBOURNE (L)
ABEL CASE PAWLICKl BALLARD P. KREUTZER (E)
GIAMBUSSO SHAO SPANGLER J. LEE (L)
PLANS BOYD STELLO M. MAIGRET (L)
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H ELPIN G BUILO A R b< A N S A S ARK ANS AS POWER & LIGHT COMPANY STM & LoulSIANA GrREEr8. LITrLE ROCK. A AKANSAS 722Q3. (5013 372-4311 January 17, 1975 02, j h,,
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Mr. A. Giambusso 9'
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Deputy Director of Licensing
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Office of Regulation ecmq U. S. Atomic Energy Commission paq song Washington, D. C.
20545
Subject:
Arkansas Power G Light Company Arkansas Nuclear One-Unit 1 Docket No. 50-313 License No. DPR-51 Proposed Technical Specification Changes
Dear Sir:
Enclosed for your review are several changes which we propose to make to the Arkansas Nuclear One - Unit 1 Technical Specification.
'Ihe affected Technical Specifications and bases for the changes are as follows:
Specification 2.3 and Table 2.3-1 (Pages 13 and 15 respectively)
This change reflects the as-built operation of the Reactor Protection System per AEC approval. A 5% overpower trip is now automatically set when going to a shutdown bypass vice being administrative 1y set.
Specification 3.3.5 (Pages 37 and 38)
Per Specification 3.3.3(D) and Specification 3.3.6(C), only one of two pressure instrument channels and one of two level instrument channels per core flood tank (CFT) are ever required to be operable.
Therefore, Specification 3.3.5 does not apply and CFT instrumentation should be de-leted from this specification.
Specification 3.5.2 and Figure 3.5.2-3 (Pages 48 and 48e respectively)
'lhe present Figure 3.5.2-3, Operational Power Imbalance Envelope, is not compatible with Figure 2.3-2, Protective System Maximum Allowable Set-points, as a part of the allowable operation is greater than the protective system maximum allowable setpoints. The change to this figure will result in a change to the Bases for this figure; therefore, the change on Page 48 specifies this new basis.
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Mr. A. Giambusso 2-January 17, 1975.
i Specification 4.1 Bases, Tables 4.1-1, 4.1-2, 4.1-3 (Pages 68, 72, 73, 74-75, respectively) i The change to Specification 4.1 Bases (Page 68) corrects an error in the referenced table number.
e The changes in Tables 4.1-1 and 4.1-2 are necessary for testing prior to pressurization. As previously written, to satisfy testing requirements it was necessary to do a calibration.
The test can now be done below 400 l'
psig but above 320 psig and 380 psig which is the pressure at which the interlocks are set to close the valves. The relief valve on this line is set at 450 psig which gives additional protection if both decay heat j-isolation valves fail to close and a procedural violation occurred.
The changes to Table 4.1-3 involve clarification of existing information and re-evaluation of other information.
Clarification of information requires the addition of several footnotes to this table by the following reasons:
1)
Reactor Coolant System 02 Analysis is meaningless when the system is open to the atmosphere (such as for refueling).
2)
Boron Analysis in the Spent Fuel Pool is meaningless when no fuel is present in the pool.
- 3) Secondary coolant sampling is only necessary when the Steam Generators are pressurized.
When they are depressurized, any release would be contained by the Dirty Liquid Radioactive Waste System.
Re-evaluation and making for more practical analysis involve changes to the terminology " Gross Beta and Gamma", the sensitivity limit for the Waste Gas Decay Tank and Reactor Building Purge, and the terminology " Gross (y)".
The basis for these three are as follows:
1)
The terminology " Gross Beta and Gamma" implies the additive results of independent Gross Beta and Gross Gamma determinations.
The disadvantages here are four-fold:
a)
As a_ general rule, gross gamma activity measurements are less valuable, less sensitive, and less precise than gross beta i
measurements.
This is due, largely, to the non-correspondence of gamma activity with the actual concentration of radioactive i
species in a mixed nuclide source. Tie ultimate cause of this problem is that for one nuclear disintegration only. one
. beta or one alpha particle is emitted. However, these may be any number of gammas' from zero to over ten, b)
Gross gamma measurements commonly base efficiencies on the 662 kev Cs-137 photopeak. A number thus generated will be a l
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Mr. A. Giambusso January 17, 1975 Cs equivalent number and may or may not be representative of the activity present.
Gross beta counting, on the other hand, avoids the Cs equivalent problem.
By liquid scintilla-tion counting, which has a beta efficiency of upwards of 100% for betas of greater than 150 kev, the need for reporting of " equivalent" numbers is not needed nor justified.
.c)
Of the major fission, corrosion, and/or activation products produced by nuclear facilities, essentially all decay by a beta emission. Most all decay by one or more gamma emissions.
Separate gross beta and gross gamma analyses could show activity for both a particular isotope's beta and gamma (s).
Additively, these could lead to an erroneous result in activity.
d) Gross beta, when performed by liquid scintillation, plus tritium, will additively account for _95% of soluble isotopes, excluding noble gases.
2)
The 10-11 pCi/cc sensitivity for the Waste Gas Decay Tanks and the Reactor Building Purge analyses are, for all practical purposes, unreasonable. To achieve this limit, based on a 2-sigma over background calculation with ANO-l's 3 x 3 NaI(T1) gross gamma system, would require 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of counting and 100 liters of sample.
On the other hand, a 10-minute count time and a 1000 cc sample yields a sensitivity of = 4.8 x 10-8 pCi/cc.
3)
Considering the difficulty involved with the setting up and subsequent analysis of gas samples for gross beta and that the sensitivity of gamma isotopic analysis is also 10-6 pCi/ce, it is proposed that " Gross (y)" analyses for unit vent gases be changed to " Gamma Isotopic Analysis".
Specification 4.4.1.2.5 (Page 83)
Previously, the Reactor Building equipment hatch could be open and leak l
testing of the outer door seals would be required by this Specification.
The change will prevent the requirement for leak testing the outer door seals when Reactor Building integrity is not required.
Specification 4.6.2.4 (Page 100a)
The previous Technical Specification required surveillance of only the third battery charger.
This change will apply to all three battery chargers and, due to normal operational rotation of the chargers, should require no additional surveillance requirements.
Environmental Technical Specifications Table 2-2 (Pages 2-17 to 2-19)
The changes to this table involve clarification of existing information and re-evaluation of that information already contained in the table.
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Mr. A. Giambusso January 17, 1975 The change to Footnote 5 specifies exactly under what conditions the unit vent would be sampled.
Previously this instruction was vague and subject to interpretation.
The items which were re-evaluated and changed as a result of that re-evaluation are the same as those covered by " Specification 4.1 Bases, Table 4.1-1, 4.1-2, 4.1-3" above.
Environmental Technical Specification 4.1.2.a(1)(a)3)2) (Page 4-8)
His change was omitted from those changes forwarded to Mr. A. Giambusso from Mr. J. D. Phillips on April 12, 1974. The change involves redistribut-ing the sampling days.
It will not reduce the number of sampling days and will provide better data, both quantitatively and qua_itatively as well as provide for unusual river or weather conditions.
Environmental Technical Specification 4.2.10 and Table 4-2 (Pages 4-15 and 4-28, respectively)
Liquidation and/or sale of farms from which samples are collected require Environmental Technical Specification changes to be made.
In order to alleviate repetitive changes to the same specification, this change will eliminate specifically named farms in the Environmental Technical Specifications but will specify those farms used for sampling purposes in the Semiannual Operating Report.
Environmental Technical Specifications Table 4-3, Figure 4-3 (Pages 4-29, Figure 4-3) n e " Sample Frequency" on Table 4-3 did not correspond to the text requirement (4.1.2.a(1)(a)3)c)) for the trap net survey. This change cor-rects that error.
Also, the " Sample Station #" for the Gill Net Survey, Trawling Survey, Trap Net Survey, Cove Rotenone Survey, Shoreline Seine Survey, and Fish Cage Survey indicate that these surveys are to be done at points ranging in number from eight to twelve.
Input to this sampling program indicates monitoring is being done in areas rather than at sample points.
In order to correlate this data with Table 4-3 and Figure 4-3, " Areas" rather than " Sample Stations" are shown for the above mentioned surveys on Table 4-3 and corresponding areas have been added to Figure 4-3.
Sample Station #19 has been moved on this figure also to correct an error in location.
These changes, individually or collectively, will cause no effect on plant operation or environmental impact.
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Mr. A. Giambusso
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January 17, 1975 Your comments and/or concurrence 'with these proposed changes are requested.
Very truly y}og'rs,,
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LL j J. D. Phillips Senior Vice President i
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STATE OF ARKANSAS
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SS COUNTY OF PULASKI
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J. D. Phillips, being duly sworn, states that he is a Senior.Vice President of Arkansa's Power & Light Company; that he is authorized on the part of said Company to sign and file with the Atomic Energy Commission this Supplementary Informa-tion; that he has read all of the statements contained in such Information, and that all such statements made and matters set forth therein are true and corr _ct to the best of his know-ledge, information and belief.
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D. Phillips SUBSCRIBED AND SWORN TO before me, a Notary Public in and for the County and State above named this /7 day of he_m 1975
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Notary Public My Commission Expires :
March 1, 1978
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