ML20199K987

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs Re Vessel Hydrostatic Pressure & Leak Testing Operability Requirements
ML20199K987
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
ML20199K978 List:
References
NUDOCS 9802090069
Download: ML20199K987 (7)
v • d • e


Text

,

R1 S-299

, to NG-98-0167 Page 1 of 2

'. ' PikOPOSED CIIANGE RTS-299 TO Tile DUANE ARNOLD ENERGY CENTER TECHNICAL SPECIFICATIONS The holders oflicense DPR-49 for the Duane Arnold Energy Center propose to amend Appendix A (Technical Specificatians) to said license by deleting certain current pages, replacing them with the attached new pages, and adding a new page (3.17-1) as described in the List of Affected Pages given below.

LIST OF AFFECTED PAGES 4

1.0-2 1.0-11 3.17-1 t

SUMM ARY OF CilANGES:

The following list of proposed changes is in the order that f changes appear in the Technical Specifications (TS).

Pace Descrintion of Chances 1.0-2 Revises the definitions of COLD CONDITION and COLD SHUTDOWN to state that,"During the performance of vessel hydrostatic pressure and leak testim the reactor coolant temperature may be considered NA, the reactor may be pressurized above atmospheric, and the reactor may be considered to remain in a COLD CONDITION / COLD SHUTDOWN if the requirements of 3.17.A a e met."

1.0-11 Adds note (g) to the AVERAGE REACTOR COOLANT TEMPERATURE column of Table 1.0-1 which states, "During the performance of vessel hydrostatic pressure and leak testing the reactor coolant temperature may be considered NA and te reactor may be considered to remain in COLD SHUTDOWN if the requirements of 3.17.A are met."

e 9802090069 980203 PDR ADOCK 05000331 P

PDR

RTS-299 to NG-98-0167 Page 2 of 2

'. 3.17-i Adds a new section,3.17, VESSEL llYDROSTATIC PRESSURE AND LEAK TESTING which will require that the following remain OPERABLE during the performance of hydrostatic and leak testing: the Secondar;; Containment Isolation Functions Reactor Vessel Water Level - Low, Refuel Floor Exhaust Duct -

liigh Radiation, and Reactor Building Exhaust Shaft - High Radiation; Secondary Containment; Secondary Containment Autc matic Isolation Dampers; Standby Gas Treatment; and two low pressure core cooling pumps (Core Spray and/or LPCI) capable ofinjecting into the vessel. In addition, Surveillance Requirement 4.17.A.1 will require that the Secondary Containment Isolation Functions be channel tested every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during the performance of hydrostatic pressure and leak testing.

DAEC-1 5, OPERABLE-OPRABILf TY

A s'ystem, suesystem, train, comoonent or devict shall be OPERABLE or have OPERASILITY when it is capable of performing its specified function (s).

in this definition shall be the assumotion that all necessary attendant Impi.

instrumentation, controls, normal and eseqency electrical power sources or seal water, lubrication cr other auxiliary emutpoent that are required for the

, cooling capable of performing their related support function (s). system, su A verification of OPERASILITY is an aaministrative chect. ty examination of appropriate plant records (logs, surveillance test reemds), to determine that a system, subsystem, train, component or device is not inoperable.

6. OpfRt.Tig Operating means that a system or component is performing its intended functions in its required manner.

7 IMEDIATE

!amediate means that the required action wili be initiated as toon as practical considering the safe operation of action.

Se unit and the importance of the required B

8. REACTOR DOWER OPFRATION Reactor power operation is any operation with the mode switch in the "Start or "Run" position with the reactor critical and above 15 rated power.

a) SINGLE L000 OpFRAT10N (SLOh of the two recirculation loops in operation.R" ACTOR POWER OPERATION w

9. HOT STANDBY CON 0fYTON Hot standby condition means operation with coolant temperature greater than 212 F, reactor vessel pressure less than 1055 psig, and the mode switch in the Startun/ Hot Stanomy position.
20. COLD CONDITION Reactor coolant temperature ewal to or less than 212*F.b
11. HOT SHUTDOWN The reactor is in the shutsown mode and the reactor coolant temperature gr than 212*F.
12. COLD SHUTDOWN The reactor is in the shutdown mode, the reactor coolant temperature equal to o less than 212*F, and the reactor vessel is vented to atmosphere. (i) 7s, y~

~

D '~Durd +ho vedo<ma,ns J uswfh d sk

><<.5sur<

w la k 4n % 6. n uh, cook ~+ u,+, a.gdr o f

\\

n w=2 kwudd%A y

s-t G c.

V1Q 'O frLS$JYl5"Y T ko u c "'

b r OG f u~ G ; Cruf O C.

Yu C e,$0 v' WQ Cb p $ t c & ha r~d W

& IP 2

(,O p bg'()O M /[Ov D $ ld VYDOW N pp. _a s s m e.Co[()

I Y eu.

_ in m

{

4-

/._~____- --

/ *

=

. ~

AUG T\\ n rm

1 DAEC-1 TABLE 1.0-1 OPERATING MODES REACTOR MODE SWITCH AVERAGEREACTORC00L6HT OPERATING MJOE POSITION TEMPERATUREm s 1.

RUN/ POWER OPERATION Run NA 2.

STARTUP Startup/ Hot Standby or NA Refuel)

3.

HOT SHLTDOWN(*)

Shutdown""*

> 212*F 4.

COLD SP.UTDOWN(*)

Shutdown""d"*)

s 212*F 5.

REFUELING (b)

Shutdowa or Refuel"""

NA (a) Fuel in the reactor vessel with the reactor vessel head closure bolts fully tensioned.

(b) Fuei in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

(c) The reactor mode switch may be placed in the Run, Startup/ Hot Standby or Refuel position to test the switch interlock functions and related instrumentation provided that the control rods are verified to remain fully inserted by a second licensed operator.

(d) The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled or withdrawn provided that the one-rod-out interlock is OPERABLE.

(e) The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Specific:. tion 3.9.A.

(f) The reactor mode switch may be placed in the Startup position for demonstration of shutdown margin per Specification 4.3.A.I.

mmm vmmmm

}$y v'ef 4 & p rybe PM [g b d

hy;

-Q j'a c e PMW e t o v etfi e

+a+;g & a:ek cuwA 4que ~=y h c~ t h~ r* M y.ask ~

Le coas, & / fs re m ala,~ :' ot b 5 HeJT bo +1 < 9 1b c

,f 3 r7. A % m.d, "

re9,ar,,,,

~

AMENDMENT N0.198 1.0-11 Ag

DAEC-1 4

1.lMITING CONTITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.17 VESSEL llYDRCSTATIC PRESSURE AND 4.17 VESSEL llYDROSTATI"' PRESSURE AND 1 EAK TESTING LEAK TESTjNJ Annlicability :

6pplicability:

Applies to the performance of ASME required Applies to the surveillance requirements during the reactor vessel hydrostatic prersure and leak testing.

performance of ASME required reactor vessel hydrostatic pressure and leak testing.

Specification:

Speci6 cation:

A.

System Avai: bility A.

System Availability 1,

Prior to and while exceeding 212'F during the 1.

Channel checks shall be performed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> performance of vessel hydrostatic pressure and leak on the Reactor Vessel Water Level-Low, Refuel testing, the following requirements must be met:

Floor Exhaust Duct - High Radiation, and Reactor Building Exhaust ShaQ - liigh Radiation trip

a. The Reactor Vessel Water Level-Low, Refuel functions Floor Exhau>t Duct - liigh Rsiation, and Reactor Building Exhaust Shatb HigG.adiation trip functions shall be operable and,
b. Secondary Containment shall be operable, and
c. Secondary Centainment Automatic isolation Dampers shall be oprable, and
d. Both trains of Standby Gas Treatment shall'.e operable, and
c. Two Icw pressure core cooling pumps (any combination of Core Spray and INCI) shall be operable and capable ofinjecting into the vessel.

2.

If Speci6 cation 3.17.A.1 cannot be met, immediately suspend activities that could increase average reactor coolant te~perature or pressure and reduce the average reacte coolant temperature to s 212'F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.17-1 a

~

RTS 27' to.

NG-98-0167 PageIofI l

SAFETY ASSESSMENT I

By letter dated February 3,1998,IES Utilities Inc. submitted a request for revision of the

. Technical Specifications (TS) for the Duane Arnold Energy Center (DAEC). The proposed amendment would modify the definition of COLD CONDITION anc.' COLD

. CONDITION and add a new section,3.11, VESSEL IlYDROSTATIC PRESSURE AND LEAK TESTING, to allow required vessel hydrostatic pressure and leak testing to be performed with reactor coolant temperatures above 212'F.

Evaluation:

Since the hydrostatic or leak tests are performed at low decay heat values the stored energy in the reactor core will be very low. Under these conditions, the potential for failed fuel is minimized. The proposed changes are consistent with NUREG 1433 Rev.1, Improved Standard Technical Specifications, and the DAEC submittal for Improved Technical Specifications. Therefore, based upon tiu above, we have concluded that the proposed revision to the DAEC TS is acceptable.

b, e

l q.

RTS-299

  • to NG 98-0167 Page1of1 ENVIRONMENTAL CONSIDER ATION 10 CFR Section 51.22(c)(9) identifies certain licensing and regulatory actions which are eligible for categorical exclu, ion from the requirement to perform an environmenta!

assessme t. A proposed amendment to an operating license for a facility requires no

__k environmental assessment it operation of the facility in accordance with the proposeu g

amendment would not: (1) involve a significant hazards consideration; (2) result in a significant change in the types er significant increase in the amounts of any efnuents that may be released offsite; 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 h

The change meets the eligibility criteria for categorical exclusion set forth ia 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 signifcant 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.

a 3.

The proposed changes will not appreciably change the way the plant or its systems are operated. There will be no significant increase in either individual or I

cumulative occupational radiation exposure.

l

_ _ - - - -

Retrieved from "https://kanterella.com/w/index.php?title=ML20199K987&oldid=4085277"