ML19254E074
| ML19254E074 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/18/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 7910310044 | |
| Download: ML19254E074 (4) | |
Text
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j UNITED STATES y-NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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OCTCCER. 8 GN D cket No. 50-313 0
Mr. William Cavanaugh, III Vice President, Generation and Construction Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203
Dear Mr. Cavanaugh:
We have reviewed yoar submittals dated April 24, May 16, June 6 and June B,1979, concerning your requests for amendments and Technical Specification changes to Facility Operating License No. DPR-51 for Arkansas Nuclear One, Unit No.1, as a result of IE 79-05A, IE 79-05B and the Order of May 17, 1979.
Ir. order to complete our review, we need additional information. You are requested to provide the enclosed additional infomation within 30 days of receipt of this letter.
Sincerely, J
?>
f Robert W. Reid, Chief I@
Operating Reactors Branch #4 i
Division of Operating Reactors
Enclosure:
Reauest for Additional Infomation cc w/ enclosure:
See next page 1235 055 D$f 7910310
.g
Arkansas Power & Light. Company cc:
Phillip K. Lyon, Esq.
House, Holms & Jewell 1550 Tower Building Little Rock, Arkansas.
72201 Mr. David C. Trimble Manager, Licensing Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas
'2203 Mr. James P. O'Hanlon General Manager Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 Mr. William Johnson U. S. Nuclear Regulatory Commission P. O. Box 2090 Russellville, Arkansas 72801 Mr. Robert B, Borsum Babcock & Wilcox Nuclear Power Generat on Division i
Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Troy B. Conner, Jr., Esq.
Conner, Moore & Corber 1747 Pennsylvania Avenue, N.W.
Washington, D.C.
20006 Arkansas Polytechnic College Russellville, Arkansas 72801 i235 056
Enclosure REQUEST FOR ADDITIONAL INFORMATION ARKANSAS NUCLEAR ONE, UNIT NO. 1 1.
In your proposed Technical Specifications (TS), Sections 4.8.1, the operability of the emergency feedwater (EFW) trains, and hence the limiting conditions for operation, are determined by surveillance requirements on specific com-ponents within the trains. Our position is that the following additional revisions should be made to these in order to address the concerns of the bulletins and orders issued since Three Mile Island with regards to EFW:
a.
Add a surveillance requirement for the EFW flow instrumentation which states when the detectors will be calibrated and tested, b.
Revise your requirements to include that the trains shall be tested on a staggered test basis.
2.
We have some concern as to the capability of your turbine driven EFW pump to cool the plant down to the RHR cut in temperature of 280 F since ? sat for 280 F is approximately 50 psia. Demonstrate that your turbine driven EFW pump has this capability or provide a TS that requires an additional appro-priate action during a cooldown when only the turbine driven ER4 pump is a vailable.
3.
Your revised TS for limiting conditions for operation (LC0) in Section 3.5.1.7 regarding the operability of the reactor trip circuitry upon loss of main feedwater or turbine trip as written allows power operation (10 to 20%) when either of these trips are inoperable.
Revise items 1, 2 and 3 as follows such that the trips may be bypassed up to these power levels but not inoperable and such that hot shutdown is the required action within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> rather than 24:
1.
Reactor trip upon loss of main feedwater shall be operable (as determined by Specification 4.1.a, items 2 and 36 of Table 4.1-2) at >5% reactor power.
(May be bypassed up to 10% reactor power).
~
2.
Reactor trip upon turbine trip shall be operable (as determined by Specie fication 4.1.a. items 2 and 42) at >5% reactor power.
(May be bypassed up to 20% reactor power.)
3.
If the requirements of Specifications 3.5.1.7.1 or 3.5.1.7.2 cannot be met, restore the inoperable trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or bring the plant to a hot shutdown condition.
3a.
Provide the basis for the bypass setpoints of 10 and 20% power for the loss of main feedwater and turbine trips anticipatory reactor trips.
4.
Your proposed TS do not include the revised temperature / pressure limits of Appendix G which are to be applied during emerger y conditions (do not shutdown HPI flow until system pressure is twice that allo.< d by the previous brittle fracturelimits). Revise your specification? to clude new emergency tempera-1235 057
. ture/ pressure limits. The revised specifications should clearly indicate when the emergency limit is to be applied, and when the previous Appendix G limit applies.
5.
Verify that the number of acceptable scrams as limited by the TS include the additional scram functions (that is, reactor trip on main turbine trip and reactor trip on main feedwater pump trip).
If not, provide a 1ist for these additional scram functions.
6.
The proposed TS do not address station operation with the electromatic relief isolation valve closed or electromatic relief valve inoperable.
In this regard, include reporting requirements for a special report on the status of a power operated relief valve which has been inoperable or isolated for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when reactor coolant system pressure is above the low reactor coolant system pressure trip setpoint associated with the reactor protection system. This report is to be prepared and submitted to the staff within 10 days following inoperability or isolation of the power operated relief valve for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
7.
For all the proposed TS changes, provide a revised bases Section in your TS that support the proposed changes.
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