ML20090K775

Proposed Tech Specs 3.4.11, RCS - RCS Vents & 6.9.2, Reporting Requirements - Special Repts

ML20090K775
Person / Time
Site:	Davis Besse
Issue date:	03/13/1992
From:	CENTERIOR ENERGY
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ML20090K767	List: ML20090K765 ML20090K772 ML20090K775
References
NUDOCS 9203190294
Download: ML20090K775 (8)

Text

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..Doce.c t Number 50-346. -.

License Kumber NPF-3 Serial Number 2026 Attachment 1 Page 6 REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM VENTS LIMIT NG 00NDITION FOR OPEPJTION 3.4.11 Tr.e following reactor coolant system vent paths shall be operaole:

, a. Reactor Coclant System Loop 1 vith vent path through valves RC 4608A

, and RC 4608B.

b. Reactor Coolant System Loop 2 vith vent path through valves RC 4610A

,' and RC 4610B.

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j Pressurizer; vith vent path through EITHER valves RC11 and RC 2A (PORV)

OR valves RC 239A and RC 200.

liAPPLICABILITY: Modes 1, 2 and 3 m _ _ _ _

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>4.4 aA6d %d Aho C y b p. ) Vith D ef R

d: :: vent pathlfanoperatile, restore the inoperable

!i vent patT to 6EODEE~statuNs. Tsin 30 days, or, be in 80T STANDBT

( vithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in 80T SHWDOVN vithin the folloving 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

i h' c. g. ( Vith two of the above vent paths inoperaole, restore at least one of

) the inoperable vent pathL to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in l 4[

p j HOT STANDBY 'vithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in 80T SHUIDOVN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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A[ d cr. \( Vith three of the above vent paths inoperable, restore at least tvo o

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c the inoperable vent paths to OP1'dABLE status within 77. hours or be in l HOT STANDBT vithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in 80T SHtTIDWN vithin the following 30 nours. -

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q( -#y The provisions of specification 3.0.4 are r.ot applicable. j {

o ll StTRVEILLANCE REQUIREMDfts i

4.4... Each reactor coolant system vent path shall be demonstrated OPERABLE at 1

Mleast once per 18 months by:

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1. Verifying all manual isolation valves in each vent path are locked in

j tne open position, and

! 2. Cycling each valve in the vent path through at least one co=olete cycle j ] i of full travel frot the control room during COLD SHITIDOVh or REFLTLING.

and 1

l 2. Verifying flov through the reactor coolant vent system vant paths t

during COLD SBUTDOVN or REFUELING.

DAVIS-3 ESSE. UNIT 1 3/4 4 32 Amendment No. 55.' 2:

9203190294 920313 PDR ADOCK 05000346 p PDR

M ket Number'50-346' License Number NPF-3 Serial Number 2026~

' Attachment 1

. Page 7 New 3.4.11 Action

a. Vith either' vent path a or vent path b inoperable (but not both),

restore the inoperable vent path to OPERABLE status within 30 days,

-or prepare and' submit a Special Report to the NRC pursuant to Specification 6.9.2 vithin the next 30 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring-the vent path to OPERABLE status, n

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. License Number NPF-3 Serial th:aber 2026 Attachment 1 '

Page 8

."AC7CR COOLANT SYSTEM II""hirA"if l \ ,U, ; . . . : ( ~ . . )..; ..;

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2ASES 10 STRUCRTdL Q'TEGRITY The inspection programs for ASHI Code Class 1, 2 and 3 components, er. cept.

steam generator tubes, ensure that the structural integrity of tL:se

ceponents will be maintained at an acceptable level througnout the life

,; ci-:ne plant. To the extent applicable, the inspectico program for these components is in compliance with Section XI of the ASME Boiler end Pressure

'lessel Code, is ji The internals vent valves are provided to relieve the pressure generated

.l by steaming in the core following a LOCA so that the core remains suffi-

!{' ciently covered. Inspection and manual actuation of the internals vent valves 1) ensure OPERABILITY, 2) ensure that the valves are not stuck open

during normal operation, and 3) demonstrates that the valves are fully j;  ; open at the forces equivalent to the differential pressure.s assumed in the safety analysis.

l 3.4.e.11 HIGH POINT \TNTE 1 l1The Reactor Cooient System high point vents are installed per NUREG-0737

' item II.B.1 requirements. The operabilitv of the system ensures capability

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of venting steam or conconcensable gas bubbles in the reactor cooling system to restore natural circulation following a small break loss of coolant accident. .

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..t l JAVIS-3 ESSE. L' NIT '. E 1/; -Il Amencment Nc. F5 l- .

Docket, Number 50-346 License Number NPF-3 Serfel Number 2026 Attachment. 1 '

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[?f!?! Ufq M 'f _ UJ0f /Z ADMINIST?).TIVE CCf."TROLS SPECIAL F.EPMTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission in accordance vith 10 CTR 50.4 vithin the time period specified fcr eten report. These reports shall be rubmitted covering the activities identified belov pursuant to the requirements of the applicable reference specification:

a. ECCS Actuation, Specifications 3.5.2 and 3.5.3.

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b. IncperableSeiwieMonitoringInstrumentation, Specification 3.3.3.3.

c. Inoperable Meteorological Monitoring; Instrumentation, Specif!:atien 3.3.3.a.

d. Seismic event analysis, Specification 4.3.3.3.2.

I e. Fire Detection Instrumentation, Specification 3.3.3.8.

} f. Fize Suppression Systens, Specifications 3.7.9.1 and 3.7.9.2.

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g. Dose or dose commitment exceedences to a MEMBER OF THE PUBLIC f ree

' radioactive materials in liquid effluents released to UNREST 71CU:D i{ AREAS (Specification 3.11.1.2).

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! h. The discharge of radioactive liquid vaste withott treatment and in excess of the limits in Specification 3.11.1.3.

1. The calculated air dose from radioactive gar.es exceeding the limits in Specificatien 3.11.2.7..

j. The calculated dose from the release of iodine-131, tritium, anc

-f radionuelides in particulate fore with half-lives grecter than i days.

-; in gaseous effluents exceeding the limits in Specification 3.11.2.3.

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!! k. The discharge of radioactive gaseous vaste without treatment anet in

! excess of the limits in Specification 3.11.2.4.

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'{ l. The calculated doses from the release of radienettve materials in

.i liquid or gaseous cifluents exceeding the limits in Specification

,{ 3.11.4 1

!! u. The level of radioactivity as the result of plant ef fluents in an t

environmental sampling mediuta exceeding the reporting levels o f Table

>! 3.12-2 (Specification 3.12.1). _ ma ,  %~.,.- 4

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DAVIS-BESSE. UNIT 1 6-18 Amendment tio. 9 Z2. f 3. 26.106.1 H

Docket Number 50-346-License Number NPP.3

.. Serial Number 2026 l Attachment 2  :

Page 1 ENVIRONMENTAL ASSESSMENT . ,

I Identification of Proposed Action i i

This proposed action involves the Davis-Besse Nuclear Power Station (DBNPS), Unit Number 1, Operating License Number NPF-3, Appendix A. _

Technical Specifications (TS). A license amendment !3 proposed to revise the Action statements for TS 3.4.11, Reactor Coolant System -

Reactor Coolant System Vents. Specifically, the proposed amendment vould allov continued plant operation without one of the Reactor  !

Coolant Sfstem (hCS) hot leg loop vent paths (either through Loop 1 l valves RC 4608A and RC 4608B, or through Loop 2 valves RC 4610A ard RC 4610B) for more than 30 days. The current Action statement requires that a vent path be restored to operable status within 30 days, or the p . ant placed in Hot Standby (Hode 3) within six hours and flot Shutdovn (Mode-4) witi'n the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

The proposed amendment vould add a new Action statement requirement

-that if an RCS loop vent path was nct rostored within 30 days, a Special Report would be submitted to the Nuclear Regulatory Conmission K (NAC) pursuant to TS-6.9.2 vithin the next 30 days describing the action taken, the cause of the inoperability, and the plans and L schedule for restoring the loop vent path, Technical Specification 6.9.2.vould also be amended to-add a rnquirement for submittal of this Special Report.

Need for the Proposed Action t The changes proposed are needed to allow continued plant operation beyond 30' days and avoid an unvarranted plant shutdown due to the inoperability of one of the two RCS loop vent paths.

Environmental Impact of the Proposed Action During normal plant operation che two RCS loop vent paths are isolated -

-by=tvo solenoid-operated valves on each of the vent paths. These

solenoid-operated vslves can be remotely operated from the control room-i= to vent noncondensible ga es from-the RCS. The loop vent paths are

. routed.to the containment atmosphere-in at unobstructed area. A manual

' valve in each-path upstream of-these solcooid-operated valves is locked ,

open.during Modes'1 through ? plant operation.

'.Inlthe event one RCS vent ~ path is inoperable, the present. Technical Specifications vill only allov continued plant operation under these circumstances.for 30 days. At that time-the vent path must-be restored or the plant shutlovn. For example, should the manual valve in one of the-RCS vent paths be closed to mitigate RCS leakage'past the solenoid-operated valves to the containment atmosphere,' the present'TS vould require either shutting down the plant or re-opening the manual 4 valve within 30 days (provided the leakage requirements of Technical

-Specification 3/4.4'6.2,-RCS - Operational Leakage veri- met). ,

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-Oceketl Number 50-346 License Number NPF , _ Serial Number 2026

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Attachment:

2 Page l' The_ proposed amendment-to TS 3.4.11 would remove the requirement of a

< ' plant shutdown in the event that either the RCS Loop 1 or the RCS Loop 2 vent path (but-not both) is inoperable for longer than 30 days. The RC9 vent _'pathr, can be used to help restore natural circulation conditions in11oving an event in which natural circulation was lost due to noncondensible gas collection. As stated in the DBNPS Updated

-Safety Analysis Report (USAR) Section 5.5.10.2, redundancy of one RCS Loop vent path is provided by the other RCS Loop vent path. However, ,

as described in USAR L 3.3.1.4, design basis events do not generate

-sufficient'noncondensible gases to block natural circulation. The RCS vent' paths ares accordingly, not r quired by the USAR to function to mitigate a Design Basis Accident. Since the RCS Loop vent path's only safety function is to act as part of the RCS pressure boundary, the inability to open the vd ves or to vent the RCS via these flovpaths _

vill have nn adverse offeet on safety, therefore the present TS requirement to shu'dovn the plant with only one of the two RCS Loop-vcnt paths inoperable is overly consarvative.

The Continuous Vent Line serves to transport steam and noacondensible gases from the reactor vessel upper head to the inlet plenum of Steam Generator-(SG) 1-2 and to improve flov in the reactor vessel upper head region during natural circulation cooldovn. Relocation of steam and gases to the RCS loop could cause an interrt:ption of naturel circulation to'RCS Loop 2 ducing a small break loss of coolant accident (LOCA) However, the DBNPS cmall break 10CA analyses have taken credit for reflux. cooling (coupled haat transfer from the RCS to the SG secondary-side)-to keep the rebetor cooled. Toledo Edison haa previously submitted-information to the NRC (Serial No. 1543 tated August 23. 1988)-regarding the effectiveness of reflux cooling.

Consequently, therr is no snecide need to be able to remove the steam or noncondensible ga vs transpotsea from the reactor vessel upper head to the RCS loap high point by the CVL. Therefore, removal of the l requirement to shutdown the plant if a RCS Loop vent path becomes inoperable has no adverse effect on safety.

, The proposed change vill-reduce the potential fvr unduly requiring-

- cooldovw and ~ heatup trauitions o f piant equipn.ent , thus preserving the cycling matgin between M ant design and_ actual operating history. -The proposed change vill also allow repairs to an (noperable RCS vent path to be deferred to a. refueling outage when the tadiation dose rate associated with the' repair can ie betta planned and scheduled in order to minimize individual and occupatlonal doses in accordance 1.ith the_As Lov Ar-Reasonably I.chievaole (ALARA) Program.

< _The proposed amendment invulves.a change to a requirement _vith respect

-to the use of a facility compenent located eithin the restricted area as-detined'in-10CFR Part-20. As disannea in the Significant Hazards Ccnsideration, this preposed amendment does nnt involve.a significant l-hasards consideration. The proposed _ change to a'11ov continued plant i

operation vith one RCS ventipath inuperable does not alter source

terms, contai?'ent laolatton oa allowab'le-releases. Accordingly, l

changing the Action statemera and reporting requirements does not

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Docket Number 50-346

• - License NumberLNPF '

Seri'al Number 2026 Attachment 2 Page 3 involve an increase in the amounts, and no change in the t: pes, of any radiological effluents that may be allowed to be released affsite.

Furthermore, there is no increase in the individual or curulative occupational radiation exposure.

With regard to potential non-radiological impacts, the proposed-amendment involses no increase in the amounts or change in types of any non-radiological effluents that may be released offsite, and has no other envitonmental impact.

Bared on the above, Toledo Edison concludes that there are no significant radiological or non-radiological environmental impacts associated with the proposed emendment.

Alternatives to'the Proposed Action Since Toledo Edison has concluded that the environmental ettects of the proposed action are not significant, any alternatives vill have only

- similar or greater environmental impacts. The principal alternative vould be not to amend the TS. This vould not reduce the environmental impacts attributable to.the facility.- Furthermore, it would necessitate that either personnel enter containment with the reactor at pover to restore a vent path'or, if necessary, force a shutdown of.the facility in accordance with the preser+ TS to effect repairs to restore a vent path. Under these circumstances, occupational exposures to

. plant' personnel'vould be incurred at a higher dose rate than if the repairs were' deferred to a refueling outage.

- Alternative Use of Resources

' This' action does not-involve the use of resources not previously

' considered in the Final Enviconmental Statement Related to the Operation of the Davis-Besse Nuclear Power Etation, Unit Number 1 (NUREG.75/097).

FindingJof No Significant Impact

. Toledo' Edison has reviewed the proposed license. amendment against the criteria of 10CFR51.30 for an envirinmental assessment. As demonstrated above, the proposed-amendment-does not involve a

'significant hazards consideration, does not increase the. types or-amounts of effluents-that may be released offsita, and does not increase.individualior cumulative occupational radiation exposures.

Accordingly,' Toledo Edison finds that the proposed license amendment, if approved by the Nuclear Regulatory Commission, vill have no

, significant impact on the environment and that no Environmental Impact

. Statement is required.

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