ML19241B316
| ML19241B316 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear |
| Issue date: | 04/13/1979 |
| From: | Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Whitt K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| FOIA-79-98 NUDOCS 7907160062 | |
| Download: ML19241B316 (3) | |
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UNITED STATES NUCLEAA REGULAToHY CoMMisSIO84 g
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April 13. 1979 MEMORANDUM FOR:
rtni Whitt IE:HQ FROM:
G.
. HadYen, Chief. Reactor Operations and Nuclear Support Branch, RIV
SUBJECT:
ARKANSAS POWER AND LIGHT COMPANY RESPONSE TO IE BULLETIN No.79-05A - ITEMS 1 - 46 AND 5 Region IV h s reviewed the licensee's response to IE Bulletin 79-05A.
Since A
the plant is scheduled for cold shutdown refueling conditions until April 30, 1919,' the implementation of the Bulletin action items will not be in place until prior to heatup above 2000F.
Regbn IV will verify ccmpletion of corrective actions as they are completen.
Region IV conrnents on the licensee's response are -as follows:
Question 1) Review of THI Event problem areas (1. 6) question, the licensee has addressed each of the In response to this identified on pages 1 and 2 of IE Eulletin 79-05A.
Item l - Emergency _Feedwat_er (EF)
Region IV takas no issue With the licensee's response; however, :he following items have been identified during our review.
There are not two redundant EF trains to each of the Steam Generators.
There are two EF pumps (1-Steam.1-Electric).
The electric is not fed from an essential bus and is mnually started.
The steam driven EF ptrnp is the only automatically started pump. The auto-start function is a part of the ICS wnich is not Class 1E.
The Technical Specification. Section 3.4.1, would appear to allow taking out both EF pumps for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, thereafter followed by an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to be in hot shutdown.
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K. Whitt. IE:HQ " " -b
- April 13, 1979
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Region IV personnel have found some errors / emissions in the operating procedures which are being responded to by the licensee. These are in addition to those identified by the 1icensee.
There is some concern that recirc valve failure cuy lead to over-pressure conditions in this system.
Item 2 - Pressurizer _ Electer.stic Relief (ER) Valve Unless Region IV receives other guidance on the licensee's proposed action to isolate the ER valve in the event of safety injection, the Region will verify the licensee's implementation of this commitment.
I_ tem 3 - Pressurizer Level Indica _ tion Region IV will verify licensee procedure revisions and training.
Item 4 - Reactor __ Building Isolation The licensee has infonned the Region that other systems such as the Quench Tank wi.ll be addressed in their forthcomi_ng April 16, 1979 response to Question 6 (IE Bulletin 79-05A).
Region IV will verify licensee procedure revisions and training.
Item 5_ - Intermittent Oper_atiion of the High Pressure Safety Injection Pumps See coment on Questions 4.a and.b (IE Bulletin 79-05A) below.
Item 6 - Trioping of Reactor Coolant Pumps Will be addressed in licensee's April 16, 1979 response.
Question 2) D_ avis Besse Event It is noted that the control system involved in precluding this transient
,is non-Class IE, i.e., the Integrated Control System.
Question 3) Review of Operating Procedures.
Region IV will followup on procedure revisions and training as each item committed to in this response is empleted.
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K. Whitt. IE:HQ April 13, 1979 Question 4) Review of Operating Procedures 4a) Region IV will followup on procedure revisions and training as each item coemitted to in this response is completed.
4b) Region !Y will followup on procedure revisions and training as each item cccmitted to in this response is completed.
It is noted that the licensee has added a third condition under which High Pressure injection may be secured. The acceptability of this response will hav9 to be decided prior to startup from the present refueling outage.
Qu_estion 5) Review of Safety-Related Valve Positions The licensee, as the result of Region IV questions has stated that their forthcoming April 16, 1979 response will amend their response to this question to include the:
Reactor Building Cooling System Reactor Building Penetration Ventilation System Hydrogen Purge system One valve was found cuitted in the operating' procedures for the Hydrogen Purge System by Region IV.
The licensee will make procedure reivsions.
Afd%w G. L. Madsen, Chief.
Reactor Operations ar.d Nuclear Support Branch e
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