ML19241B301
| ML19241B301 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/14/1979 |
| From: | Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Jordan E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19241B299 | List: |
| References | |
| FOIA-79-98 NUDOCS 7907160017 | |
| Download: ML19241B301 (3) | |
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G. l. Had;cn, Chief, Reactor Op.: rations Md lh; clear Support Branch, RIV
SUBJECT:
ARidNSAs P0tlER AND tiGHY C0:4PAdY RESP 0nSE TO IE DULLETIN Ho 79-05A - ITGS 4c AND d. AJID G - 12 Region !Y has revicued the licensee's response to IE Buliotin 79-0LA, dated April 6,1979.
Sinr;e the plant is schtduled for cold shutdown refueling conditions until April 30, 1979, the ir.ipirmentation of the Bulletin rction items will not be in place until prior to heatup above 2000F.
Region IV will ytrify completion of correctivo actions, procedurt revis ie rio.trsil this n.oosiated tro isiirty ua Wecas i t.cma as u wwylated.
Region IV coimaats on the licensee's response are as follows:
Ita.n 5 - Review of Safety-Related Valve Positioning Requirper.g, The licensee has included a supplemental response to item 5, indicating that thay have reviewed the Reactor Building Cooling Systcm, the Reactor Building Penetration Room Ventilation Systen, and the Hydrogen Purge Systcm, as rcquantad by Cagion IV.
Jtem f.c -_ Reactor Cooltnt Pumo Operation The licensee has rs:sponded to this itc n for th.'ce conditions:
break site exceeding HPI capacity, bresk sixo within HPI capacity, and other (e.g., Main Steam Line Break).
For been sizes within llPI capacity, the licensee proposes to keep at
,least one RCP per loop in cperation until the system has be.en stnble for 20 minutes and the hot and cold leg temperatures are at least 500F below saturation.
This proposal should be eval-u&ted by the NRC to determine if it is acceptable.
For accidents such as a thin Steam Line Break, the licensee states that tripping of the RCP's is nei:as;;ar,y to lessen the severity pf the accident.
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E. L. ilordt.n, IE:HQ April 18. 1979 Item 4d - Operator Reliance Jfenn_ Pressurizer Level The licensee is revising plant procedures, placing czphasis upea assuring an adcquate r.argin to saturation conditions..They are developing two' mathods to aid the operator in assessing core conditions relative to voiding.
Both of the methods out.lin9d appear to have merit.
If other PWR licensces have not developed AP&L methods,a f m414t* raouwdo,!
it in t coormtended tfoot Umy be f ea rbr nee.d u r unt Item 6 - Containment Isolation Initiation '
Region IV agrees with the licenseo's evaluation of which contain-ment penetrations should receive an ES signal to isolate en low RC pressure.
liowever, the licensee does not believo thht the accessar design change can be incorporated during the current cutata and has ccMitted to incorporate the design change during the first outage to cold shutdown conditions (after complation of the destga change engincarir.g) which is of sufficient length to accommdats the change but not later than the next refueling outage.
If this timing is detemined to be acceptable, Region IV will rsuite that the licensee make emergency procedure revisions to includ.c folloxup actions after a LOCA to verify that the valves listed in itens 9 through 16 of the licensee's response are closed.
Item 7 - Gnargency FeedwateLSystem Valves The licensco's rescondo is considarnd en be aoooptabia.
Item 8_- Indep_ondent Emago,cy Feedwater Flownnths The licensec's response to this itsa and the proposed action stata-rcents are acceptable to Region IV, but the conm2nts listed unifor Item 1 of our memo of April 13.-1979, still apply.
' Item 9 - Transfer _ of, Potentially Radioactive Casos and liquids Out_-of-contairmont The licensee's response to this ite;n is acceptable to RN ion IV.
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Rem 10 - fiaintenance and Test Procedures, The licensco's response to this itsu is acceptable to Region IV.
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E. L. Jordan IE:lQ
-h Aprt! 10, 104 Item 11 - Oparating and Ibintenanco Personnal Training a
Region IV is continuinti to follow the licensee's progress in c04-pletion of the training requirements of IEB 79-05A.
rrompt xeporting proconures for nut: notirie.acion or unii i t.
Serious Events In accordance with Item III.B.S of TI 2595/2, Regicn IV uill.~ requi
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that all plant operators and supervisory personnal receive additic training in the provisions and directives for early NP.C notificati i
of ser'ious events.
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G. L. Ibdson, Chief, i
Reactor Operations and Nuclear Support Branch i
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