ML19327B529

Application for Amends to Licenses DPR-51 & NPF-6,adding Limiting Conditions for Operation & Surveillance Requirements for Main Steam Line Radiation Monitors,Per Generic Ltr 83-37

ML19327B529
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/19/1989
From:	Tison Campbell ARKANSAS POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19327B530	List: ML19327B529 ML19327B533
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM 0CAN108908, CAN108908, GL-83-37, NUDOCS 8911010064
Download: ML19327B529 (7)

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i " . , gs Athenoes i Power & Light Company

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..-/ 425 West Capatil P.O. Bow 551 Little Rook. Arkansas 72203

• cf. Tel 601377 3525

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[. T. O. Campbell E*N.'r"**'

! October 19, 1989 p.

SCAN 198988 U. S. Nuclear Regulatory Commission

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Documer.t Control Desk-Mail Station P1-137 . '

Washington, DC 20555 l

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SUBJECT:

Arkansas' Nuclear One - Units 1 & 2

. Docket Nos. 50-313 and 50-368

, License Nos. DPR-51 and NPF-6

Proposed Technical Specifications Changes -

Operational and Surveillance Requirements for the Main' Steam Line Radiation Monitors -

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Gentlemen:

. Arkansas Power & Light Company (AP&L) requests amendments to the Arkansas -.

Nuclear One, Unit I and Unit 2 Technical Specifications. The proposed  !

changes would add limiting conditions for operation and surveillance .

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requirements for each unit's main steam line radiation monitors in accordance with Generic Letter 83-37. ,

We have evaluated the proposed changes using the criteria in 10CFR50.92(c) and~have determined that said changes involve no significant hazards

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censideration.

AP&L requests that the effective date for this change be 30 days after NRC issuance of the amendment to allow for distribution and procedural revisions

, necewsary to implement this change.

Very truly yours,

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Wr T. G. Cam ell J

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TGC/1w ,

Attachments )

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8911010064 891019 \

PDR ADOCK 05000313 i P PDC An Eniergy company l l

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• U.' S. NRC ]

V 'Page 2 i i October 19, 1989

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cc: Mr. Robert Martin  !

p U.'S.~ Nuclear Regulatory Commission j Region IV

'611 Ryan Plaza Drive, Suite 1000 1 Arlington, TX 76011-NRC Senior Resident Inspector .

Arkansas Nuclear One - ANO-1 & 2 *

i. ' Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. C._Craig Harbuck NRR Project Manager, Region IV/ANO-1 U..S. Nuclear Regulatory Commission

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NRR Mail Stop 13-D-18 One White Flint North 11555 Rockville Pike Rockville, Maryland'20852

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Mr. Chester Poslusny.

NRR Project Manager, Region IV/ANO-2 >

U. S. Nuclear Regulatory Commission

-NRR Mail Stop 13-D-18 ',

One White Flint North 11555 Rockville Pike Rockville. Maryland 20852 i

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Ms. Greta Dicus, Director '

l Division of Radiation Control

and Emergency Management  ;

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Arkansas Departarant of Health 4815 West Markham Street Little Rock, AR 72201  ;

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STATE OF ARKANSAS ) ,

) SS COUNTY OF PULASKI )

I, T. G. Campbell, being duly sworn, subscribe to and :,ay that I am Vice President, Nuclear for Arkansas Power & Light Company; that I have full authority to execute this. oath; that I have read the document numbered BCAN198908 and know the contents thereof; and that to the best of my knowledge, information and belief the statements in it are true, t

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T. G. Campb SUBSCRIBED AND SWORN TO before me, a Notary Public in and for the County and State above named, this /Mday of [h ,

1989.

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Notary Public My Commission Expires:

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ATTACHMENT

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PROPOSED TECHNICAL SPECIFICATION CHANGES- i

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LICENSE AMENDME:tT REQUEST .!

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' IN THE MATTER OF AMENDING 3

, LICENSE NO DPR-51 I i

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LICENSE NO. NPF-6 [

ARKANSAS POWER & LIGHT COMPANY .

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ARKANSAS NUCLEAR ONE, UNIT 1  :

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ARKANSAS NUCLEAR ONE, UNIT 2- 1

-C DOCKET NO. 50-313 .

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DOCKET NO. 50-368 L OCTOBER 17, 1989

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, DISCUSSION

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The main steam line radiation monitors (MSLRMs) provide information on releases that might exceed the range of the N-16 monitors, monitor releases through the main. steam line code safety valves even when the main steam isolation valves are closed, and provide data to estimate airborne release rates per plant' procedure. The MSLRMs were a NUREG-0578, item 2.1.8.6  :

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recommendation to provide increased' range of radiation monitors for noble gases in plant effluent lines. NUREG-0737, item II.F.1 Attachment 1

[ addressed change; to previous requirements (i.e. , NUREG-0578 and -0660) and

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provides clarification for PWR secondary side. main safety valve and dump . 1 L. vulve discharge lines. NUREG-0737, item II.F.1 also encompassed noble gas

! effluent monitors for potential accident. release paths, such as: reactor building purge, condenser air removal system exhaust, auxiliary building, radwaste building, etc. Generic letter 83-37, "NUREG-0737 Technical Specifications" requested that limiting conditions for operation (LCO) and r

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surveillance requirements be included in licensee technical specifications '

for the noble gas effluent monitors, including steam' safety valve discharge and atmospheric dump valve discharge monitors (e.g., MSLRMs). i j In response to the Generic Letter.83-37 request'for licensees to submit

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technical specifications as appropriate for NUREG-0737 items, Arkansas Power

& Light Company (AP&L) replied by letter dated March 16, 1984 (8CAN838401).

In this letter no proposed changes for NUREG-0737, Item II.F.1.1-(noble gas monitors) were.noted as being necessary since LCO and surveillance

• requirements for the noble gas monitors were previously submitted under the Radiological Effluent Technical Specifications (RETS), dated September 30, .

RETS were subsequently approved by Amendments 88 and 60

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1983 (8CAN898318).

to the ANO-1 and ANO-2 Technical Specifications, respectively.

As requested by the NRC, AP&L met with NRC personnel on February 6 and 7,

l. '1984 to discuss AP&L's efforts to meet the NUREG-0737 guidelines including j' technical specification implementation for NUREG-0737, Item II.F.1.1. ,

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During that meeting, AP&L stated that the requirements were met by instal-lation of super particulcte iodine / noble gas (SPING) monitors which were.

included in the RETS.

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. DESCRIPTION OF PROPOSED CHANGES L For the ANO-1 Technical Specifications:

a. Add a new Specification 3.5.1.13 (p. 42b) to specify that i e main

[ steam-line radiation monitors (MSLRMs) shall be operable; i

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b. Revise Table 3.5.1-1 (pp. 45d1 and 45f1) to include limi t ; ' ions for operation and action statement for the MSLRMs; and t-

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[ c. Add a new specification 6.12.5.k to' denote that a Special Repu,

( required for inoperable MSLRMs.

h L The MSLRM surveillance requirements are to be encompassed by the existing Table 4.1-1, item 28 specification in order to maintain consistency with other radiation monitoring system requirements for ANO-1.

For the ANO-2 Technical Specifications:

a. Revise Table 3.3-6 (pp. 3/4 3-25 and 3/4 3-26) to include limiting conditions for operation and action statement for the MSLRMs; ,

b. Review Table 4.3-3 (p. 3/4 3-27) to include surveillance requirements; and

c. Add a new specification 6.9.2.n to denote that a Special Report is required for inoperable MSLRMs. ,

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I DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION

, AP&L has performed an analysis of the proposed changet in accordance with l 10CFR50.91(a)(1) regarding no significant hazards consideration, using the L criteria in 10CFR50.92(c), as follows:

e (1) The proposed changes do not increase the probability or consequences of.

l any accident previously evaluated since these radiation monitors do not provide any information that is required to safely shutdown the plant.

The monitors provide release information for evaluating offsite i emergency actions when venting via the steam safety and atmospheric

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dump paths.

(2) The proposed changes do not create the possibility of a new or l different kind of accident from any previously evaluated since failure of this instrumentation would not result in any unanalyzed accident. 1

.. This instrumentation is utilized for passive monitoring of radiation '

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levels.

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(3) 'The proposed changes do not involve a significant reduction in a margin of safety since the instrumentation does not serve a safety-related function. These changes constitute additional limitations, restrictions, or controls not presently included in the Technical Specifications, j The Commission has provided guidance for amendments that are considered not likely to involve a significant hazards consideration (51FR7750).

The proposed amendment is most closely encompassed by example (ii): "A change that constitutes an additional limitation, restriction, or control not presently included in the technical specifications, e.g. , a more stringent surveillance requirement."

Therefore, based on the above and the previous discussion of the amendment request AP&L has determined that the requested change does not involve a significant hazards consideration.

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