ML20199K960

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Proposed Tech Specs Re Standby Liquid Control Operability Requirements
ML20199K960
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 02/03/1998
From:
IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
Shared Package
ML20199K920 List:
References
NUDOCS 9802090062
Download: ML20199K960 (4)
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Text

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RTS 298 3

  • Attschment 2 to NG 98 0147 Pag:1of1 PROPOSEP Cli ANGE RTS-298 TO THE DUANE ARNOLD ENERGY CENTEP.

TECHNICAL SPECIFICATIONS The holders oflicense DPR-49 for the Duane Arnold Energy Center propose to amend Appendix A (Technical Specifications) to said license by deleting the referenced page and replacing it with the attached new page as described in the List of Affected Pages given below.

LIST OF AFFECTED PAGES .

3.4-1 -

L l

SUMMARY

OF CilANGES:

l P_ggg Descrintion of Chances 3.4 Changes 3.4.A.1 to state:"The Standby Liquid Control system shall be OPERABLE whenever the reactor is in STARTUP or RUN/ POWER OPERATION."

9802090062 980203 PDR ADOCK 05000331 P PDR l

( _ .I -U

OAEC-1

.. LDilTING CONDITION FOR OPERATION SURVEILLANCE RE001kEMENT 3.4 STAND 8Y LIQUID CONTROL SYSTEM 4.4 STANDdY LIQUID CONTROL SYSTEM Applicability: Applicability:

Applies to the operating Applies to .the surveillance status of the Standby Liquid requirements of the Standby Control System. Liquid Control System.

Objective: Objective:

To assure the availability of To verify the operability of a system w;th the capability the Stanoby Liquid Control to shut down the reactor and System, maintain the shutdown coheition without the use of control rods.

Specification: Specification: ,

A. Normal System Availability A. Normal System Availanility '

l. During periods when fuel is The operab';11ty of the Standby 1Athe reactor and prior td Liquid Control System will be i star from a COLD CON ITION, verified by the perfonnance of the St y Liquid Co rol the following tests:-

l System sh Q be OPE LE, except as sp ift in 3.4.B 1. At least once per three months l below, ihis s em need not each punp loop shall be func -

ce OPERABLE en reactor tionally tested by recirculat-is in the LD CONUI ON and ing domineralized water to the all con al rods are fu y test tank. Minimum pump flow i sitr and Specificatto _ rate of 26.2 gpm against a '

.3 '

met & s/

]s system head of 1150 psig shall be verified.

'7fic $tsscdb (I'f En (o i

\2. At least once during each 6 <,k et d jglfbe.,jfERAME OPERATIr4 CYCLE: l*

]

dwo eV 4de. MC. +Y f5 lp i a. Check that the setting of the

) system relief valves is syn.TO P c NOP 3 mom f 1350 < P < 1400 psig.

0?6 p.kT/05

  • Intent Change Only (definition of

/

d operating cycle).

RTS 4 %

Amencment No. U3. 160 3.4-1 J

RTS-298

  • Attachment 3 to NG-98-0147.

Page1 of1

- 5 SAFETY ASSESSMENT, By letter dated February 3,1998, IES Utilities Inc. submitted a request for revision of the Technical Specifications (TS) for the Duane Arnold Energy Cen;er (DAEC). The proposed amendment would change the conditions when the Standby Liquid Control system (SLC) is required to be OPERABLE to only the STARTUP and RUN/ POWER OPERATION modes.

Assessment:

As stated in the Applicability section of 3.1.7 (SLC) Bases of the DAEC submittal for Improved Technical Specifications, "In MODES I and 2, shutdown capability is required. In MODES 3 and 4, control rods are not able to be withdrawn since the reactor mode switch is in SilUTDOWN and a control rod block is applied. This provides adequate controls to ensure that the reactor remains subcritical. In MODS S, only a single control red can be withdrawn from a core cell containing fuel assemblies, o

Demonstration of adequate SDM (LCO 3.1.1, " SHUTDOWN MARGIN") ensures that tiie reactor will not become critical. Therefore, the SLC Systet is not required to be OPERABLE when only a single control rod can be withdrawn, i-With minor exceptions, the definitions of the operating modes in Table 1.0-1 of the current TS is the same as Table 1.0-1 of the DAEC submittal for Improved Technical Specifications. Therefore, the proposed change in operability requirement for SLC to RUN/ POWER OPERATIONS (MODE 1) and STARTUP (MODE 2) is consistent with NUREG 1433 Rev. I and the DAEC submittal for improved Technical Specifications.

RTS-298 Attachment 4 to NG-98-0147 j Page1or1

. 6 ENVIRONMENTAL CONSIDERATION 10 CFR Section 51.22(c)(9) identifies certain licensing anG regulatory actions which are cligible for categorical exclusion from the requirement to perform an emironmental l

assessment. A proposed amendment to an operating license for a facility requires no environmental assessment if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any efnuents that may be released otTsite; and (3) result in a significant increase in individual or cumulative occupational radiation exposure. IES Utilities Inc. has reviewed this request and determined that the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR Section 51.22(c)(9). Pursuant to 10 CFR Section 51.22(b),

no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the amendment. The basis for this determination follows:

Basis The change meets the eligibility criteria for categorical entusion set forth in 10 CFR Section 51.22(c)(9) for the following reasons:

1. As demonstrated in Attachment I to this letter, the proposed amendment does not involve a significant hazards consideration.
2. The proposed changes are consistent with NUREG 1433 Rev. i and DAEC submittal for Improved Technical Specifications. There will be no significant change in the types or significant increase in the amounts of any effluents that may be released offsite.
3. The proposed changes will not appreciably change the way the plant or its systems are operated. The:cfore, there will be no significant increase in either individual or cumulative occupational radiation exposure.

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