ML20040F207
| ML20040F207 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/19/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8202080489 | |
| Download: ML20040F207 (4) | |
Text
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h Docket No. 50-368 gj y dyu i
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l Mr. William Cavanaugh, III j'/
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' Senior Vice President Energy H
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Arkansas Power & Light Company-4 M y# r.r P. O.-Box 551 Q'/g'jT.D\\g'
,Q Little Rock, Arkansas 72203 q;I r
Dear Mr. Cavanaugh:
Your letter dated August 12,1980 ~ proposed to change Technical Specification 4.8.1.1.2.C.2 which addresses the diesel generator load block timing surveillance' test requirements. Your letter of May 9,1980 to Mr. K. V.
Seyfrit. Director, Region IV IE further states that a TS change request would be submitted in an effort to clarify the subject specification.
We have reviewed your request and conclude that we do not have adequate information to enable us to approve it at this time. The current TS r'
states that the interval between each load block shall be within + 10 percent of its design interval. An inspection of FSAR Table 8.3-T and I
your August'12,1980 submittal indicated for example, that the first five loads are sequenced onto the diesel generator at five second intervals. Therefore, the current TS would require that for each of I
these loads the time delay relay should actuate within S 1 0.5 second following actuation for the previous load. The requirement of the current TS is that the tolerance of i10 percent is applied to the interval between successive loads and not to the elapsed time between a
l time =0 and application of a given load.
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At this time there appear to be several options for resolving this i
matter. One option would be to implement the current TS in the manner i
specified above. A second option would be to provide additional infor-mation supporting the AP&L Co interpretation of the TS as provided in the AP&L Co letter to Mr. Seyfrit dated May 9,1980. Tbts interpre-l i
tation applied the i10 percent-of-interval tolerance to the total i
elapsed time for each load. This additional information should address the reconmendation of Regulatory Guide 1.9 with respect to the restora-tion of diesel generator voltage and frequency following each load. The information may be in the form of analysis or sufficient operating test data which adequately demonstrates the capability of the diesel generator to recover within the load intervals and should extend out to at least 4
90 seconds beyond time =0.
A third option would be to provide additional p
j infomation supporting the TS change request of August 12, 1980 as identified above for. the second option. We note thet the application of the tolerances in the AP&L Co's August 12, 1980 letter cist significantly l
d1fferent from the app 1 cation discussed in the AP&L Co's May 9, 1980 o,,,m,.......> etter..
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. To support our comunications on this matter we have prepared the enclosed table which provides a comparison between (a) the current TS requirement, (b) the AP&L Co's May 9,1980 letter interpretation and (c) the AP&L Co's August 12, 1980 letter proposal.
Please provide a response within 30 days of receipt of this letter regarding your plans for resolving this matter.
In the meantime, it istthe staff's position that the current ANO-2 Technical Specifi-cation requirements are as listed in the first column of the enclosure,
" Current TS".
Sincerely, Original signed by Robert A. Clark Robert A. Clark, Chief Operating Reactor Branch #3 Division of Licensing
Enclosure:
As stated cc: See next page DISTRIBUTION:
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Arkansas Power & Light Company cc:
Mr. David C. Trimble Manager, Licensing Arkansas Power & Light Company F. O. Box 551 Little Rock, Arkansas 72203 U.S. Environmental Protection Agency Mr. James P. O'Hanlon Region VI Office General Manager ATTN:
Regional Radiation Arkansas Nuclear One Representative P. O. Box 608 1201 Elm Street Russellville, Arkansas 72801 -
Dallas, Texas 75270 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420 7735 Old Georgetown Road S. L. Smith, Operations Officer Bethesda, Maryland 20014
- Arkansas Nuclear Planning &
Responsa Program Nicholas S. Reynolds, Esq.
P. O. Box 1749 c/o DeBevoise & Liberman Russellville, Arkansas 72801 1200 Seventeenth Street, N.W.
Washington, D. C.
20036 Arkansas Polytechnic College Russellville, Arkansas.72801 tir. Charles B. Brinkman Manager - Washington Nuclear Operations C-E Power Systems 4853 Cordell Avenue, Suite A-1 Bethesda, Maryland 20014 O
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Enclosure AP&L Co AP&L Co Current May 9, 1980 August 12, 1980 T5 Interpreta* Ton TS Proposal 1 M0V's 0
0 0
Service Water Pump
-0.5 5 + 0.25 5 + 0.5 5 + 0.5 (90%)
(80%)
(70%)
10 + 0.25 10 + 0.5 10 + 1.0
~
(90%)
(80%)
(50%)
LPSI Pumps 15 + 0.25 15 + 0.5 15 + 1.5
~
(90%)
(80%)
(30%)
Cont. Cooling Fans
-2.0 20 + 0.25 20 + 0.5 20 + 1.5 (90%)
(80%)
(20%)
Cont. Spray Pumps
-0.25
-0.5
-2.5 25 + 1.25 25 + 2.5 25 + 0.0 (90%)
(80%)
(80%)
ChargingPumps(A&B)
-1.25
-2.5
+ 5.0 50 + 0.50 50 + 1.0 50 -
(90%)
(80%)2 (10%)
Charging Pump (C)
+ 0.5
-4.0 60 -
60 + 1.0 60 + 8.0 (90%)
(80%)2 Five Loads 70 + 0.5
'70 + 1.0 Not provided (90%)
(80%)2 Five Loads 80 + 0.5 80 + 1.0 Not provided (90%)
(80%)2 EFW Pump (Diesel #1
-13.0 only) 90 + 0.5 90 + 1.0 90 + 5.0 Note 1: '4ith these tolerances the interval between loads could be the hidicated percentage of the design interval. This should be 90% or higher to meet current TS requirements.
Note 2: These numbers extrapolated from AP&L Co criteria contained in the May 9, 1980 letter.
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