ML20147H445
| ML20147H445 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/02/1988 |
| From: | Dick G Office of Nuclear Reactor Regulation |
| To: | Tison Campbell ARKANSAS POWER & LIGHT CO. |
| References | |
| TASK-2.K.3.05, TASK-TM GL-86-06, GL-86-6, TAC-49676, NUDOCS 8803080483 | |
| Download: ML20147H445 (4) | |
Text
March 2,1988 0
Docket No. 50-368 Mr. T. Gene Campbell Vice President, Nuclear Operations Arkansas Power end Light Corpany Post Office Box 551 Little Rock, Arkansas 7??03
Dear Mr. Campbell:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION, PEACTOR COOLANT PUMP TRIP, tRKANSAS NUCLEAR ONE, UNIT ? (TAC. NO. 49676)
After reviewing your response (November 24,1986,2CAN118608) to Geretic letter 86-06, Implemertation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps", we find that we need additional inforration so that we may ccrplete our review.
Please provide answers to the enclosed questions within 50 days of the date of this letter.
The reporting ard/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, isl George F. Dick, Jr., Project Manager Project Directorate - IV Division ef Reactor Project - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation Erelosure:
As stated cc w/ enclosure:
See next page Distribution Doctet File.
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Mr. T. Gene Campbell Arkansas Power & Light Company Arkansas Nuclear One. Unit 2 CC:
Mr. J. Ted Enos. Manager Mr. Charles B. Brinkman. Kanager Nuclear Engineering and Licensing Washington Nuclear Operations Arkansas Power & Light Company C-E Power Systems P. O. Box 551 7910 Woodmont Avenue Little Rock. Arkansas 72203 Suite 1310 Bethesda Marylano 20814 Mr. James M. Levine. Director Site Nuclear Operations Mr. Frank Wilson. Director Arkansas Nuclear One Division of Environmental health P. O. Box 608 Piotection Russellville. Arkansas 72801 Department of Health Arkansas Department of Health Mr. Nicholas S. Reynold:
4815 West Markham Street Bishop. Liberman, Cook. Purcell Little Rock. Arkansas 72201 1200 Seventeenth Street. N.W.
Suite 700 Honorable William Abernathy Washington, D.C.
20036 County Judge of Pope County Pope County Courthouse Regional Administrator. Region IV Russelville. Arkansas 72801 U.S. Nuclear Regulatory Comission Office of Executive Director for Operations 611 Ryan Plaza Drive. Suite 1000 Arlington. Texas 76011 Senior Resident Inspector U.S. Nuclear Regulatory Comission 1 Nuclear Plant Road Russellville. Arkansas 72801 Ms. Greta Dieus. Director Division of Environmental Health Protection Arkansas Department of Health 4815 West Markam Street Little Rock. Arkansas 72201 Mr. Robert B. Borsum Babcock & Wilcox huclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814
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ADDITIONAL QUESTIONS ON APKANSAS POWER AND LIGHT'S RESPONSE TO GENERIC LETTER 86-06 FOR ARKANSAS NUCLEAR ONE, UNIT 2 1.
Arkansas Power & Light's (APlLL's) letter of Novenbar 24, 1986 did not clearly identify which of the criteria presented in CEN-268 was select.ed to trip the second set of pumps during a small break LOCA (SBLOCA) at Arkansas Nuclear One, Unit 2 (ANO-2).
Identify the criterien selected and the setpoints used te determine when to trip the second set of pumps. Also, identify the pressure setpoint used to trip the first set of pumps if different from that recomerded in CEN-268, 2.
For the instrumer.tation identified in response to question 1 discuss how the effects of irstrueent uncertainty, as identified in AP&L's McVember ?A, 19P6 response to Generic Letter (GL 86-06 item ?) were included in determining the setpoints for pressure, subcooled margin, and sacerdary reactivity.
3.
AP&L did not provide sufficiert infomation in its November 24, 1986 response to GL 86-06 iten 3 to datemine how the uncertaintiet, in the generic analysis presented in CEN-?68 affect the results as they apply to ANO-2. Therefore, identify the ANO-2 plant specific features not representative ef the reference plant used in the analyses presented in CEN-268. At a minimum discuss core power; decay heat; HPIS capacity; makeup flows; setpoints for reactor trip, safety injection, and accumulator infection and show that the values used in the generic analysis are either representative of those at ANO-? or conservative.
If a reference plant pararater is not representative for ANO-2, discuss how this was considered in detemining the plant specific setpoints.
4.
Part 2 of Item 4 of Generic Letter 86-06 requested the licensee to identify, '... procedures which provide direction for use of individual steam generators with and without operating RCPs."
Ir its Nevertar 24, 1986 response. AP&L stated that because all four RCPs are not tripped for transients that cause use of individual steam generators and the first two purps tripped are always in opposite loops, use of individual steam generators has to relationship to RCP trip criteria. Because the ANO-2 procedures will always allow era pump in a loop to be operating in situations where a single stear generator will be used, identifying all procedures and operator trairing that involve use of single stean generators is sufficient to comply with this item. The licensee is requested to provide this infnreation.
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5.
In itt resterse to item 4. API,L stated that energency operating procedura (EOP) 2?02.01 requires the ure of reactor coolant pump trip guidelines.
Identify what situations, i.e.. Pain steen line breah, stear generator tube ruptures, small break LOCAs, etc., are covered by E0P 2202.01.
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