ML19332A815

Application for Amend to License NPF-6,mofifying Surveillance Requirements of Tech Spec 4.6.2.3 to Assure Operability of Containment Sys.Class III Amend Fee & Supporting Documentation Encl

ML19332A815
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/11/1980
From:	Cavanaugh W ARKANSAS POWER & LIGHT CO.
To:	Clark R ARKANSAS POWER & LIGHT CO.
Shared Package
ML19332A816	List: ML19332A815 ML19332A818
References
2-090-13, 2-90-13, NUDOCS 8009180424
Download: ML19332A815 (6)

Text

3 ARKANSAS POWER & LIGHT COMPANY POST OFRCE BOX 551 UTTLE ROCK. ARKANSAS 72203 (501)371-4422 September 11,1980 WILLIAM CAVANAUGH 111 Vice President Generation & Construction 2-090-13 Director of Nuclear Reactor Regulation ATTN: Mr. Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Subject:

Arkansas Nuclear One-Unit 2 Docket No. 50-368 License No! NPF-6 Technical Specification Change Request (Filt. 2-1510)

Gentlemen:

Arkansas Nuclear One-Unit 2 (ANO-2) Technical Specification 3.6.2.3 requires, as a minimum, "two independent containment cooling groups shall be OPERABLE with two cooling units in one group and at least one cooling unit in the second group".

Recently questions have arisen with regard to the adequacy of the Surveillance Requirements of Specification 4.6.2.3 to assure the operability requirements of the specification are met. In particular, the Surveillance Requirement (4.6.2.3.a.3) requires a verification of service water flow rate > 2500 gpm to each group of cooling units.

(Each group of cooling units consists of two cooling units). The specification allows one group to contain only one operable cooling uni t. When the group is operating in this configuration no current '

Technical Specification surveillance requirement is provided to assure OPERABILITY. Verification has been provided through the review of design documents that in the above configuration (one cooling unit operable in a group) only 1250 gpm of sersice water flow is necessary to assure OPERABILITY of the group to design basis requirements.

8009180 Q2Y MEMBER MOOLE SOUTH UTluTIES SYSTEM f

Mr. R. A. Clark Srpt:mber 11, 1980 Accordingly, attached is an ANO-2 Technical Specification Change Request which modifies the surveillance requirements of specification 4.6.2.3 to provide specific surveillance requirements to assure OPERABILITY of the Containment Cooling Groups in all operating configurations allowed by the subject specification.

Further questions ha' s resently arisen with regard to the adequacy of the allowed minimum )erable groups of containment cooling units (CCU) to meet the design basis requirements of AN0-2.

Section 6.2.2.1 of the ANO-2 FSAR specifies the following as the minimum containment heat removal capability to assure limitation of peak contain-m(nt pressures (following a DBA LOCA or MSLB) to within containment design pressure.

1. all four CCUs ; or,

2. two loops of CSS; or

3. two of four CCUs and one loop of CSS The information as currently reflected in the FSAR Section 6.2.2 is basically the design requirements as of the filing of the ANO-2 FSAR.

Subsequent to this . original filing (and before issuance of the ANO-2 Technical Specifications) additional containment peak pressure analyses were performed to justify Technical Specification 3.6.2.3 as it now exists. These new analyses were discussed with NRC in the final devel-opment of the existing specification and were used by the NRC as bases for the existing specification. The revised analyses are partially docu-mented in FSAR Table 6.2-11 (amendment No. 47, June 16,1978) s howing .

that only three CCUs were assumed OPERABLE in the Containment Peak Pressure analyses.

More recenth , additional Containment Peak Pressure analyses (now con-sidered the design basis analyses for ANO-2) have been performed using the COPATI A code as described to NRC in Bechtel Power Corporation's Topical Rup/rt BN-TOP-3. Input assumptions to the code cases are shown in Table 1.

A parametric case study was performed for varying combinations of contain-ment spray system (CSS) loops and CCUs,each demonstrating a peak contaimnent pressure less than the design pressure of 54 psig. These analyses are shown on Table 2. -

In accordance with 10CFR50.71, we are now in the process of completely updating the ANO-2 FSAR. All information pertinent to this issue will be updated in the FSAR and submitted to the NRC in accordance with the above regulation, i

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Mr. R. A. Clark September 11, 1980 We have determined the attached Technical Specification Change Request to be a Class III Amendment in accordance with 10CFR170.22. Accordingly, also attached is a check in the amount of $4,000.00.

Ver truly yours s k <g h William-Ca naugh IIIj WC:JTE:tw Attachments

STATE OF ARKANSAS )

) SS COUNTY OF PULASKI )

William Cavanaugh, III,-being duly sworn, states that he is Vice President, Generation & Construction, for Arkansas Power &' I Light Company; that he.is authorized on the part of said Company to sign and file with the Nuclear Regulatory Commission this Supplementary Information; that he has reviewed or caused to have reviewed all of the statements contained in such information, and that all such stata-ji ments made and matters set forth therein are true and correct to tha best of his knowledge, information and belief.

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William Cagpfaugh, III 4

SUBSCRIBED AND SWORN TO before me,.a Notary Public in and for the County and State above named, this // day of . f;bx y1980.

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$thL A/// $ Af dotary Public / /

I My.C'ommission Expires:

My Commission Expires' 9/1/g1 i

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TABLE 1 ANALYSES INPUT ASSUMPTIONS Safety Injection Flow * - Full flow of two trains Service Water Inlet Temperature ** - 120F All other appropriate input parameters are within Technical Specification Limits

• Conservative assumption for Case 3 on Table 2 since the failure of 1 diesel generator is not consistent with operation of 2 safety injection trains .

• • Conservative assumption for Cases 1-3 on Table 2 as:

1. Technical Specification 3.7.4.1 limits service water temperature to < 100F

2. FSAR Figure 9.2-19 demonstrates the service water temperature is considerably less than 120F at the time the peak containment.

pressure occurs (minutes into the accident) l

l- TABLE 2 ANO-2 CONTAINMENT' PEAK PRESSURE ' ANALYSES

'# CSS Loops #CCUs Peak Pressure Case 1* 2 0 52.2 psig Case 2** 1 3 52.3 psig Case 3***- 1 1 52.8 psig

• Current Technical Specifications preclude operation in this configuration even when assuming the most limiting single failure. This case is overly conservative and presented only for information.

• • Current Technical Specifications allow operation in this configuration for only 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. .

• • • This case represents the minimum configuration allowed by the Technical Specifications assuming the single-failure of one diesel generator.

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