ML20217B824

Proposed Tech Specs Re Requirements for Alternate Shutdown Panel & Associated Auxiliary Feedwater Panel

ML20217B824
Person / Time
Site:	Fort Calhoun
Issue date:	03/18/1998
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20217B815	List: LIC-98-0044, Forwards Application for Amend to License DPR-40,revising & Combining Sections 2.15(4) & 2.15(5) to Clearly Address Regulatory Requirements for Alternate Shutdown Panel & Associated Auxiliary Feedwater Panel ML20217B818 ML20217B824
References
NUDOCS 9803260187
Download: ML20217B824 (8)

Text

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2.0 LIMITING CONDITIONS FOR OPERATION 2.15 Instmmentation and Control Systems (Continued) ventilation isolation signals available if the containment ventilation isolation valves are closed. If after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from time of initiating a hot shutdown procedure the inoperable engineered safety features or isolation functions channel has not been restored to operable status, the reactor shall be placed in a cold shutdown condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This specification applies to the high 4

rate trip-wide range log channel when the plant is at or above 10 % power and is operating below 15% of rated power.

(3) In the event the number of channels of a particular system in service falls below the limits given in the columns entitled " Minimum Operable Channels" or

" Minimum Degree of Redundancy", except as conditioned by the column entitled

" Permissible Bypass Conditions", the reactor shall be placed in a hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; however, operation can continue without containment ventilation isolation signals available if the ventilation isolation valves are closed.

If minimum conditions for engineered safety features or isolation functions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from time of discovering loss of operability, the reactor shall be placed in a cold shutdown condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the number of operable high rate trip-wide range log channels falls below that given in the column entitled " Minimum Operable Channels" in Table 2-2 and the d

reactor is at or above 10 % power and at or below 15% of rated power, reactor critical operation shall be discontinued and the plant placed in an operational mode allowing repair of the inoperable channels before startup or reactor critical operation may proceed.

If, during power operation, the rod block function of the secondary CEA position indication system and rod block circuit are inoperable for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or the plant computer PDIL alarm, CEA group deviation alarm and the CEA sequencing function are inoperable for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the CEAs shall be withdrawn and maintained at fully withdrawn and the control rod drive system mode switch shall be maintained in the off position except when manual motion of CEA Group 4 is required to control axial power distribution.

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4 U.S., Nuclear Regulatory Comission LIC-98-0044 ATTACHMENT B

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DISCUSSION, JUSTIFICATION AND NO SIGNIFICANT HAZARDS CONSIDERATION

. DISCUSSION AND JUSTIFICATION Omaha Public Power District (0 PPD) is proposing revisions to the Fort Calhoun Station Unit No.1 Technical Specifications (TS) section 2.15(4) pertaining to

'the. Alternate Shutdown Panel AI-185 and section 2.15(5) pertaining to the Auxiliary Feedwater Panel AI-179 (

Reference:

Fort Calhoun Station's LER 97-002, Charging Pump Outside Technical Specification for the Alternate Shutdown Panel, dated May 14,1997). The current revision of Technical Specifications sections do not adequately address the regulatory requirements for the two panels.

Only indication functions for Wide Range Logarithmic Power, Source Range Power, Reactor Coolant Cold Leg Temperature, Reactor Coolant Hot Leg Temperature, Pressurizer Level, Volume Control Tank Level, Steam Generator Wide Range Level, Steam Generator Narrow Range Level, Steam Generator Pressure, and Pressurizer Pressure are addressed. The sections do not address either the control functions for Charging Pump-flow or Auxiliary Feedwater flow.

The sections, as written, can cause overlooking of the intention of the Alternate Shutdown System.

When the Charging Pump CH-1B, for instance, is out of service, it is possible that no Limiting Condition for Operation is entered for Technical Specifications Section 2.15(4),simplybecausethepumpisnotspecificallylistedinthesection.

The proposed changes to Technical Specifications Section 2.15(4) and 2.15(5) will clarify the scope of the Alternate Shutdown Panels.

The changes will identify:

(1) all indication functions and control functions required for the alternate (remote) shutdown system, (2) panel location:: of the functions, and (3) the number of channels required. The Limiting Conditions for Operation (Operability and Shutdown Requirements) for the Alternate Shutdown Panel and the Auxiliary Feedwater Panel are not being changed.

The applicable modes are not being changed.

However, Sections 2.15(4) and 2.15(5) are being combined.

The proposed changes do not affect Table 3-3A in Section 3.0 pertaining to the Surveillance Requirements for the the Alternate Shutdown Panels (AI-185 and AI-212) and the Auxiliary Feedwater Panel (AI-179).

The table already fully addresses the equipment located on the panels.

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.g BASIS FOR N0 SIGNIFICANT HAZARDS CONSIDERATION:

The proposed changes to the Fort Calhoun Station (FCS) Unit No.1 Technical Specifications (TS) are in accordance with the corrective action described by LER 97-002.

The proposed changes to Sections 2.15(4) and 2.15(5) are also consistent with the technical content and format of Section 3.3 of the NUREG 1432 containing the improved Standard Technical Specifications for Combustion Engineering Plants.

The proposed changes do not involve significant hazards consideration because operation of FCS in accordance with these changes would not:

(1)

Involve a significant increase in the probability or consequences o',' an accident previously evaluated.

The proposed changes to Technical Specifications Section 2.15(4) and 4

2.15(5) identify functions, instruments, and controls along with their location and the number of required channel s.

The new Technical Specifications section addresses the regulatory requirements for equipment required for Alternative and Dedicated Shutdown Capability per 10CFR Part 50 Appendix R.

It will ensure that proper Limiting Conditions for Operation are entered for equipment-or functional inoperability.

There are no physical alterations being made to the Alternate Shutdown Panel and the Auxiliary Feedwater Panel or related systems..Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

(2)

Create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed changes will not result in any physical alterations to the Alternate Shutdown Panel or the Auxiliary Feedwater Panel, or any plant configuration, systems, equipment, or operaticnal characteristics.

There will be no changes in operating. modes, or safety limits, or instrument limits.

With the proposed changes in place, Technical Specifications retain requirements for the Alternate Shutdown Panel and the Auxiliary Feedwater Panel.

Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.

2.

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.(3). : Involve _a; significant reduction in a margin'of. safety..

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The-proposed changes clarify : the regulatory requirements. for the

. Alternative:and Dedicated Shutdown Capability as defined by 10CFR Part 50, Appendix R.

The. proposed ~ changes wi_11: not alter any physical; or.

' operational characteristics-of the Alternate Shutdown Panel 'and the l Auxiliary Feedwater Panel and their. associated systems and ' equipment.

s Therefore, the proposed changes do not involve.a~ reduction in a margin.of-safety.

Basedi on the above considerations,, the' proposed amendment does ~ not ' involve

.significant. hazards considerations as defined by 10 !.FR Part 50.92 and the -

(proposed changes will'not result in a condition which significantly alters.the

-impect.of the. Station on the environment..Thus, the proposed changes meet the.

eligibility criteria-for' categorical exclusion set forth in 10' CFR Part:

151.22(c)(9) and pursuant to 10 CFR Part 51.22(b) no environmental assessment need be prepared.-

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