3F0209-06, License Amendment Request 310, Revision 0: Application to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Technical Specification

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License Amendment Request 310, Revision 0: Application to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Technical Specification
ML090620582
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 02/26/2009
From: Young D
Progress Energy Florida
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
3F0209-06
Download: ML090620582 (32)
v • d • e


Text

Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: 10 CFR 50.90 February 26, 2009 3F0209-06 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Crystal River Unit 3 License Amendment Request #310, Revision 0:

Application to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-490, Revision 0, "Deletion of E Bar Definition and Revision to RCS Specific Activity Technical Specification"

Reference:

The B&W Owners Group to Nuclear Regulatory Commission Letter dated September 13, 2005, "TSTF-490, Revision 0, 'Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec"'

Dear Sir:

In accordance with the provisions of Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), Florida Power Corporation (FPC), doing business as Progress Energy Florida, Inc., is submitting a request for an amendment to the Improved Technical Specifications (ITS) for Crystal River Unit 3 (CR-3). The proposed changes would replace the current ITS 3.4.15 limit on RCS gross specific activity with a new limit on RCS noble gas specific activity.

The noble gas specific activity limit would be based on a new dose equivalent Xe-133 definition that would replace the current E Bar average disintegration energy definition. In addition, the current dose equivalent 1-131 definition would be revised to allow the use of additional Committed Effective Dose Equivalent dose conversion factors.

The changes are consistent with NRC-approved Technical Specification Task Force (TSTF)

Change Traveler, TSTF-490, Revision 0, "Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec." The availability of this Technical Specification improvement was announced in the Federal Register on March 19, 2007 (72 FR 12838), "Notice of Availability of Model Application Concerning Technical Specification Improvement Regarding Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification Using the Consolidated Line Item Improvement Process."

Attachment A provides a description and assessment of the proposed changes, as well as confirmation of applicability. Attachment B provides the existing ITS pages and ITS Bases marked-up to show the proposed changes. Attachment C provides final ITS pages and ITS Bases pages.

No new regulatory commitments are being made in this submittal.

Progress Energy Florida, Inc.

Crystal River Nuclear Plant 15760 W. Powerline Street Crystal River, FL 34428

U.S. Nuclear Regulatory Commission 3F0209-06 Page 2 of 3 The CR-3 Plant Nuclear Safety Committee has reviewed this request and recommended it for approval.

FPC requests approval of the proposed license amendment by June 30, 2009 with the amendment to be implemented during Refuel 17, scheduled for Fall 2011. This LAR is required to support submittal of the EPU LAR. It has been determined to be a linked submittal for the EPU LAR per Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-109, "Acceptance Review Procedures."

In accordance with 10 CFR 50.91, a copy of this application, with enclosures, is being provided to the designated State of Florida Official.

If you have any questions regarding this submittal, please contact Mr. Dan Westcott, Supervisor, Licensing and Regulatory Programs at (352) 563-4796.

(

~

~

'Dale E. Young Vice President Crystal River Nuclear Plant DEY/par Attachments:

A. Description and Assessment B. Proposed Improved Technical Specification Changes (Strikeout and Shadowed Text Format)

C. Proposed Improved Technical Specification Changes (Revision Bar Format) xc:

NRR Project Manager Regional Administrator, Region II Senior Resident Inspector State Contact ITSB Branch Chief

U.S. Nuclear Regulatory Commission 3F0209-06 Page 3 of 3 STATE OF FLORIDA COUNTY OF CITRUS Jon A. Franke states that he is the Director Site Operations, Crystal River Nuclear Plant for Florida Power Corporation, doing business as Progress Energy Florida, Inc.; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information, and belief.

Jon A. Franke Director Site Operations Crystal River Nuclear Plant The foregoing document was acknowledged before me this day of 2009, by Jon A. Franke.

S&L/~1 Signature of Notary Public State Q

io-ida CAROLYN E. PORTrMANN Notary Public - State of Florida Commission Expires Mar 1, 2010

  • 7~-

Commission # DD 524380 Bonded 8By National Notary Assn.(

(Prinitjy~e,-or-stap con'mirrssioncu Name of Notary Public)

Personally Produced Known

-OR-Identification

PROGRESS ENERGY FLORIDA, INC.

CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 LICENSE AMENDMENT REQUEST #310, REVISION 0 APPLICATION TO ADOPT-TECHNICAL SPECIFICATIONS TASK FORCE (TSTF) TRAVELER TSTF-490, REVISION 0, "DELETION OF E BAR DEFINITION AND REVISION TO RCS SPECIFIC ACTIVITY TECHNICAL SPECIFICATION" ATTACHMENT A DESCRIPTION AND ASSESSMENT

U.S. Nuclear Regulatory Commission Attachment A 3F0209-06 Page 1 of 3 Description and Assessment

1.0 DESCRIPTION

This letter is a request to amend Operating License DPR-72 for Crystal River Unit 3 (CR-3).

The proposed changes would replace the current limits on primary coolant gross specific activity with limits on primary coolant noble gas activity. The noble gas activity would be based on DOSE EQUIVALENT XE-133 and would take into account only the noble gas activity in the primary coolant.

The changes were approved by the Nuclear Regulatory Commission (NRC) staff Safety Evaluation (SE) dated September 27, 2006 (ADAMS ML062700612) (Reference 1). Technical Specification Task Force (TSTF) change traveler TSTF-490, Revision 0, "Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec" was announced for availability in the Federal Register on March 19, 2007 (72 FR 12838) as part of the consolidated line item improvement process (CLIIP).

2.0 PROPOSED CHANGE

S Consistent with NRC-approved TSTF-490, Revision 0, the proposed ITS changes are as follows:

  • Revise the definition of DOSE EQUIVALENT 1-13 1.
  • Delete the definition of"E Bar, AVERAGE DISINTEGRATION ENERGY.
  • Add a new TS definition for DOSE EQUIVALENT XE-133.
  • Revise LCO 3.4.15, "RCS Specific Activity" to delete references to gross specific activity; add limits for DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133; and delete Figure 3.4.15-1, "Reactor Coolant DOSE EQUIVALENT 1-131 Specific Activity Limit versus Percent of RATED THERMAL POWER."
  • Revise LCO 3.4.15 "Applicability" to specify the LCO is applicable in MODES 1, 2, 3, and 4.
  • Modify ITS 3.4.15 ACTIONS Table as follows:

A. Condition A is modified to delete the reference to Figure 3.4.15-1, and define an upper limit that is applicable at all power levels.

B. ACTIONS are reordered, moving Condition C to Condition B to be consistent with the Writer's Guide.

C. Condition B is modified to provide a Condition and Required Action for DOSE EQUIVALENT XE-133 instead of gross specific activity. The Completion Time is changed from 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. A Note allowing the applicability of LCO 3.0.4.c is added, consistent with the Note to Required Action A. 1.

D. Condition C is modified based on the changes to Conditions A and B and to reflect the change in the LCO Applicability.

  • Revise. SR 3.4.15.1 to verify the limit for DOSE EQUIVALENT XE-133. A Note is added, consistent with SR 3.4.15.2 to allow entry into MODES 2, 3, and 4 prior to performance of the SR.

U.S. Nuclear Regulatory Commission Attachment A 3F0209-06 Page 2 of 3

3.0 BACKGROUND

The background for this application is as stated in the model SE in NRC's Notice of Availability published on March 19, 2007 (72 FR 12838), the NRC Notice for Comment published on November 20, 2006 (71 FR 67170), and TSTF-490, Revision 0.

4.0 TECHNICAL ANALYSIS

In the model SE, the NRC included statements that would require Florida Power Corporation (FPC) to identify specific information in support of adopting TSTF-490.

The following provides the CR-3 specific information in this regard.

1. Section 3.1.1 of the model SE includes a list of acceptable dose conversion factors (DCF) for use in the determination of dose equivalent iodine (DEI) in relation to dose consequence analysis.

The CR-3 analyses employ Committed Effective Dose Equivalent (CEDE) dose conversion factors from Table 2.1 of EPA Federal Guidance Report No. 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion."

2. In the first paragraph of Section 3.1.2 of the Model SE, a bracketed list of isotopes is provided that designates the noble gases that may be used in the determination of dose equivalent xenon (DEX).

All isotopes depicted within these brackets are currently considered in the CR-3 calculation of, DEX.

This is reflected in the proposed CR-3 definition Of DEX.

3. Section 3.1.2 of the model SE also provides two possible determination methods for DEX. CR-3 uses the effective dose conversion factors for air submersion listed in Table 111.1 of EA Federal Guidance Report No. 12, 1993, "External Exposure to Radionuclides in Air, Water, and Soil." This is also reflected in the proposed CR-3 definition of DEX.
4. Section 3.1.3 of the model SE states that it is incumbent on the licensee to ensure that the site specific limits for both DEI and DEX are consistent with the current steam generator tube rupture (SGTR) and main steam line break (MSLB) radiological consequence analyses. CR-3 is requesting this LAR for post EPU conditions which will be 0.35 ýiCi/g for DEI and 646 gCi/g for DEX as depicted in the proposed CR-3 ITS pages. These proposed changes will be implemented prior to the end of Refuel 17, scheduled for Fall 2011.

FPC, doing business as Progress Energy Florida, Inc., has reviewed References 1, 2 and 3, and the model SE published on November 20, 2006 (71 FR 67170) as part of the CLIIP Notice for Comment. FPC has applied the methodology in Reference 1 to develop the proposed TS changes. FPC has also concluded that the justifications presented in TSTF-490, Revision 0, and the model SE prepared by the NRC staff are applicable to CR-3, and justify this amendment for the incorporation of the changes to the CR-3 Improved Technical Specifications (ITS).

U.S. Nuclear Regulatory Commission Attachment A 3F0209-06 Page 3 of 3

5.0 REGULATORY ANALYSIS

A description of this proposed change and its relationship to applicable regulatory requirements and guidance was provided in the NRC Notice of Availability published on March 19, 2007 (72 FR 12838), the NRC Notice for Comment published on November 20, 2006 (71 FR 67170), and TSTF-490, Revision 0.

5.0 NO SIGNIFICANT HAZARDS CONSIDERATION FPC has reviewed the proposed no significant hazards consideration determination published in the Federal Register on March 19, 2007 (72 FR 12838) as part of the CLIIP.

FPC has concluded that the proposed determination presented in the notice is applicable to CR-3 and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a).

7.0 ENVIRONMENTAL EVALUATION FPC has reviewed the environmental consideration included in the model SE published in the Federal Register on March 19, 2007 (72 FR 12838) as part of the CLIIP. FPC has concluded that the staff's findings presented therein are applicable to CR-3 and the determination is hereby incorporated by reference for this application.

8.0 REFERENCES

1. NRC Safety Evaluation (SE) approving TSTF-490, Revision 0, dated September 27, 2006
2. Federal Notice for Comment published on November 20, 2006 (71 FR 67170)
3. Federal Notice of Availability published on March 19, 2007 (72 FR 12838)

PROGRESS ENERGY FLORIDA, INC.

CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 LICENSE AMENDMENT REQUEST #310, REVISION 0 APPLICATION TO ADOPT TECHNICAL SPECIFICATIONS TASK FORCE (TSTF) TRAVELER TSTF-490, REVISION 0, "DELETION OF E BAR DEFINITION AND REVISION TO RCS SPECIFIC ACTIVITY TECHNICAL SPECIFICATION" ATTACHMENT B PROPOSED IMPROVED TECHNICAL SPECIFICATION CHANGES (STRIKEOUT AND SHADOWED TEXT FORMAT)

Definitions 1.1 1.1 Definitions (continued)

CONTROL RODS CORE ALTERATION CORE OPERATING LIMITS REPORT (COLR)

CONTROL RODS shall be all full length safety and regulating rods that are used to shut down the reactor and control power level during maneuvering operations.

CORE ALTERATION shall be the movement of any fuel, sources, or other reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle.

These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.2.18.

Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT 1-131 DOSE EQU**ALENT I.

3--

sh1all be IIthat Uoncentration of I 131 (111[%-

ocuI es/grarn) that alone would produce the same thyroid dose as the iuant-I-ty-and isotopi miture 31 I

1:32, i

133,

-and 1 135 actually prcsentL.

The thyroid dose Ionveision factors used for this Iallulation shall be those listed in international Committee ont Radiation Protection EICRP) 30, Supplement to Part 1, page 192 21:2, Table titled, "Committed Dos Equivalent in Target Organs or Tissues per intake of Unit Acttvitv." DOSE EOUIVALENT T-131 shllh 1

(continued)

Crystal River Unit 3 1.1-3 Amendment No. 1-4-9

rL A% [RAG[

L 1%

V I--I Definitions Xe-135m-, X-e~- 15, and Xke--1-3 ac-tua))y present.

If a sp~ecific no~ble gas nuclide is not detected,,

,it shouldbe assumed toe*

e present at the mnimum

,etectable activity.- Th'determination of DOSE)

EQUIVALENT XE *133~ ' ha]T -bepe'rform~ed using

,effective dose con'viersion~ factors for ailrL-

ýsubmiersion ]isted in Table 111.1 of EPA. Fed~eral1_

Guidatnce Report NJo.-112, 1993; "External Exposr to Radionuclide~s" ir~j~ater, and Soil~

EI shall be the average (weighted in pooto to th@ concentration of aeah radionuclide in the reactor coolant at the time of sampling) ofte sum of the average beta and gamma enrie "e

disintegration (in M.V) for t

other than iodines, with half lives5 15 10inute@S, making u-p at least 95% of the total non iodine activity in the coolant.

EFPD shall be the ratio of the number of hours of production of a given THERMAL POWER to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, multiplied by the ratio of the given THERMAL POWER to the RTP.

One EFPD is equivalent to the thermal energy produced by operating the uttstN I tbK~A! t UN tNtltb.y EFFECTIVE FULL POWER DAY (EFPD)

(continued)

Crystal River Unit 3 1.1-3 Amendment No. 1-4-9

RCS Specific Activity 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Specific Activity LCO 3.4.15 The speczificz activity of the reactor coolant RCS DOSE EQU~IVALENT 1131 and DOSE EQUIVALENTF XE-133 specific activity shall be within limits.

APPLICABILITY:

MODES 1-and 2, 1, 2, 3,, and 4 MOD[ 3 with RCS average tempe rat ure(T--GF-ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

DOSE EQUIVALENT 1-131 ------------- NOTE-------

> 1.-0 Cil-tg not LCO 3.0.4.c is applicable.

A.1 Verify DOSE Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> EQUIVALENT,

-131 within the acceptable Figure 3.4.15 1 21 ipCi/g.

AND A.2 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT 1-131 to within limit.

Xi Inot wiIthin LCO 3.0.4.c is appli

.abeIe limit.*

B.1 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT XE-133 to withi n li mit.

(continued)

Crystal River Unit 3 3.4-30 Amendment No. 21-5

RCS Specific Activity 3.4.15 ACTIONS (conti nued)

CONDITION REQUIRED ACTION COMPLETION TIME B5,.

Required Action and O.1 Be in MODE 3 with 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion

< O2F.

Time of Condition A fB: not met.

AND OR C 2> _T Beours:E7 DOSE EQUIVALENT 1-131 in the unacceptable region of Fiur C. Gross specific C.1 Perform SR 3.4.15.2..

4-hours acivity %of th-e coolant not within AND C.2 Be in MODE 3 with6hor SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 V e r Ify r eaco cool

,t UU1ant14-gIros55s spiecific Only yrf4Ui red to be performed i n 7MODE1.

Veify reactor coolant D~OSE E~QUIVALENT 7

days E-133

.acivit 646.Ci-/g.

SR 3.4.15.2 NOTE---------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 14 days 1-131 specific activity pj~~Ci/g.

AND Between 2

and 6

hours after THERMAL POWER change of

Ž!

15%

RTP within a

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period Crystal River Unit 3 3.4-31 Amendment No. 1-4-9

RCS Specific Activity 3.4.15 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.15.3 NOTE Not required to be performed until 31: daysr after a mnimum of 2 [FPD and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for

-ý1 48*

hourIsII.

Il~I I

L rJ

(;IIL

£ I(L U

ýýi UI; I III I I [Il 1 L.

Crystal River Unit 3 3.4-32 Amendment No. 1-4-9

RCS Specific Activity 3.4.15 E

250 i--

S 200 U_

C1.

Cn LU"

'-- 150 0

0 0

I,... -

C) 50 100 LU 0

=1 Uf) 0

\\z UNACCEPTAB OPERATIC ACCEP BLE OPE lION___

0 PER4CdENT R RATH THEIAL OWER U

,uu Figure 3.4.15-1 (page 1 of 1)

React Coolant DOSE EQUIVALENT 1-131 Specific Activity imit Versu Percent of RATED THERMAL POWER With Reactor Coo *t Specific Activity >1.0 pCi/gm DOSE EQUIVALENT 1-131 vstal River Unit 3 3.4-33 Amendment No.

Cr 149

Complete Replacement of the Existing 3.4.15 Bases RCS Specific Activity B 3.4.15 B3. _47_REACTaR CO'O&LAT SYSTEM -0ýCS)j B3747f5RCSpecjfi7vctiI ty BW5E'S BAýKRGUROND The maximum~ d ose7T~

thti ni___

at thie exclusion dr-bounda.ry cani receive for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> following ~an accident, ra the low population Zone outer bOLundary for the ~radiological release duration, is speci~fied in 10Q CFR~ 50.67 (Ref. 1). Doses, to control~ room operators ~must be W1imited per GDC 19.

The limits on specific ac~tivity ensu~eta the offsite and con'tr6T, room doses are appropriatel li~ted during analyzed transients and accidents.

The RCS s IeI fiJ c acti viT~ tyLO miT th& t T6alI wbl e

,concentration~ level of radionuclides in the~ reactor coo~lant.,

dthe LWO limits are established to minim~ize ~the dose-]

consequences-rn the event of a steam line break (SLB)or sýte~am

_eerator tube rupture_(S¶LRY-accddent.'

L7~T~

CO cont-ai-in--s. sp'e-ifi'c,,a-c-tivitI sfrIohL5

~EQUIVALENT 17-131 anhd DOSE EQUIEVALENT XE-1-33.~ The atlow'a5Td

!levels are intended to ensure that offsite and control roomi doses meet the~ appropri.ateacceptance criteri.a i the S~tanda-r

-R'eview _Plan (Ref. 2).

-The -aaly-ses Kflor the SLB an~d 'SGTR ý_aec~ide ris-esrtWflls~h the.

acceptance liiamt's'for_ RCS,;spec'if;i*,c,-ýactivity.

Referenjý to 1h e'se' analyses 'is 'used lto Iassess e'hanhges t6totthe 'itit tat 1co..uld affect' RCS ~specific_- acti.vi

.ty,1.as they relate to the (continued)

Crystal River Unit 3 B 3.4-71 Revision No. 3-7ý

Complete Replacement of the Existing 3.4.15 Bases RCS Specific Activity B 3.4.15 OPcases of'

,jtU7reac~tor cýooIaii SAFETY ANALYSES iodine, specific activity.

One case, assumes, spe-Ci fi cF (conti nued) activty at 0.35 pCi]/g DOSE EQUIVALENT. 1-131 with ah concurrent larg& iodIne spike that increases ',the,,rate oý f release of iodine from the fuel rods contai ning-claddihng-

-- decfects to the' primary coolant immedi-ate~ly; a',fter.a-SLB -(jbv5

',a factor of 500.),. or SGTR (by a factor, of,,335),

[r.espectively:

The second case assumes "the initil eacrt coolant iodiHne activity at 21.0 6c*/g. DOSE EQUIVALENT7 1311 Sue to an iodine spike caused dbya reactor or an 'RCS tnaIs0 p.ori*ot..the a~ci&e

, In both cases, t~he'moS1e gas sgi fic ac~tivity is assumed to be. 4 ii/~

gas cspec

  • ~~a

.... sapOzoDOSE EQUIVAL" NT,, XE- - 13 3.

The SGTR~ diily assumes a rilse -ThprDeýsLsure in tfhe ruptured SG causes radioactively contam Iinaed steam to idtscharge to the atmosphere through the atmosphterc ldump valves or the main steam safety valves.

The atmospheric discharge stops when theturbine bypas~s to the conden 'se

'r' removes the excess eneg~y to ra~pidly reduce the RCS pressure and close the valves.

The unaffected Grmvs core decay heat by ven~tinp'g steam until the cooldown e

-nds; a nd the Decay Heat Remioval (DHR) system is_ place in

'service.

~TheSL~B radýT -1 og-i Cl anal ysi s assumie s t~at-6f f ste~, oiwe~r s J os t a~t the same time as the pip bireak occurs outside7'

'containment. The, affected SC blows down complete~ly a'

steam is vented directly to the atmodsphere.,The unaffecý-ted

&CGremoves core devcay heat by venting steam to th4___

tamshr ~unti~l the cool~down ends ~and the ~DHR ~systm~~

plIaced in' se rviceý.

Jpra greate Eh i

1th&eLCO -limit i~s permissible, if the ýacti v ity leel do t!

'exicgd__ZLQpjO

.for more than ~48,.hours.

T 1-TW

-m-1 -fts o n R-CS s~p'e -c i fi-c-fi~ Vitt ya re-& aT W6-sii-f0 establishi~ng stanidard~ization in raditaion shielding~and plaqnt,_per'sonnel ~radiation protection prctices.i RCS specifi1c acti vity Safi sf i esCHtriT 2o `0 F

50.36(c) (2) (1J)..

o~

f.IOC (continued)

Crystal River Unit 3 B 3.4-72 Revision No. 55

Complete Replacement of the Existing 3.4.15 Bases RCS Specific Activity B 3.4.15 ICCUA

~tat te' al'cuT~ aed does are wi TmFin

~

Violation of the Ce maypresult' in reacterccrtlanee Lradioactivity levels that ~could, fin ~the-event 'of a7-S[B-OHL KSTR, lead to doses that exc~eed> the. SRP, a~cceptance cri~te~rsi L(Ref. 2)j

-Pr DOSE, EQU.VALNT 1-131 and DOSE EQUIVALENT*;XE-133 is,__

necesisary to limit the poten~tia~l cons~equences of'a S'LB_'O-6T towthnthe SRP acceptance cri~teria (RLIY._.2_

In MODES 5 n

~i~6, the steamn gener'ato6rs are n6-ft be-g usedý6

,for decay heat removal~, the RCS and. steam geeatr ar

'dpesrzd anid primary. to ~secondary leakage is ~minimial.

T~herefore, thea Imonitoring of RCS specific -ac~tivity isnt require.~

AC-TIONS §A.

I and A.2 With the DO@SE EQUIVALENT 1-131 great~er than the LCO li-mi-t, samples at *interv~als o~f 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> mu~st be takenf to diemonstrate that the specific activity is < 21.0 P~i/g.

The Comple~tion~ Time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is requi red to ~ob~tai~n and' lanalyze

a. sample.

~SaW i ngis continued every 4 hiours to, provide_ a tr'end.,

~The D0SE'EQUIV'ALENT T-131 must be restored to w~hniii Iwithin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

The CompletionTime of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> ~i S'"

acceptable s~ince it is expected that, if therewere~a

,odine spike, the normal coolant iodine concentration W6ýld berestored ý.Ithin this time period. Also, ther~e is a low prob'abil-ity of a SIB or SGT~R ocurndrnti ie-

'p r"iodd (conti nued)

Crystal River Unit 3 B 3.4-73 Revision No. 3-7

Complete Replacement of the Existing 3.4.15 Bases T RCS Specific Activity B 3.4.15 BASIES (conti nued)

Crystal River Unit 3 B 3.4-74 Revision No. 7

I Complete Replacement of the Existing 3.4.15 Bases I RCS Specific Activity B 3.4.15 BA~SES~

ýSURVEILLANCE SR 3.4.15~.1 (contir'd REQUIREMENTS5_________________

Trending the results of thiTs iurVeiillance-aTlows pro6per Fremedial action to be taken ~bef~re 'reachi ng the LCOijlimi t unider normal operating condi ti~ons.

~TIe 7 da Frequen~cy, conides te low probability-of a gross fuel failu~re during this time.

1his allows the Su rveilI Iance' 'to' be performed in those MODES>, phio to enteffi ng MODEJ1 SR 3.4.15.

,in MODE 4, 'MODE 3, and MODE,2, prior to performi~ng theSR.,

,This allows the SUreillance to'I be -prormedIn those' (conti nued)

Crystal River Unit 3 B 3.4-75 Revision No. 7

Complete Replacement of the Existing 3.4.15 Bases RCS Specific Activity B 3.4.15 FEf'FER~ENCE-S

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Gneip-uhThir rci ent" Crystal River Unit 3 B 3.4-76 Revision No. 3-7

PROGRESS ENERGY FLORIDA, INC.

CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 LICENSE AMENDMENT REQUEST.#310, REVISION 0 APPLICATION TO ADOPT TECHNICAL SPECIFICATIONS TASK FORCE (TSTF) TRAVELER TSTF-490, REVISION 0, "DELETION OF E BAR DEFINITION AND REVISION TO RCS SPECIFIC ACTIVITY TECHNICAL SPECIFICATION" ATTACHMENT C PROPOSED IMPROVED TECHNICAL SPECIFICATION CHANGES (REVISION BAR FORMAT)

Definitions 1.1 1.1 Definitions (continued)

CONTROL RODS CORE ALTERATION CORE OPERATING LIMITS REPORT (COLR)

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT XE-133 EFFECTIVE FULL POWER DAY (EFPD)

CONTROL RODS shall be all full length safety and regulating rods that are used to shut down the reactor and control power level during maneuvering operations.

CORE ALTERATION shall be the movement of any fuel, sources, or other reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle.

These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.2.18.

Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries per gram) that alone would produce the same dose when inhaled as the combined activities of iodine isotopes 1-131, 1-132, 1-133, I-134,and I-135 actually present.

The determination of DOSE EQUIVALENT 1-131 shall be performed using Committed Dose Equivalent (CDE) or Committed Effective Dose-Equivalent (CEDE) dose conversion.factors from Table 2.1 of EPA Federal Guidance Report No.

11.

DOSE EQUIVALENT XE-133 shall be that concentration of Xe-133 (microcuries per gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present.

If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity.

The determination of DOSE EQUIVALENT XE-133 shall be performed using effective dose conversion factors for air submersion listed in Table III.1 of EPA Federal Guidance Report No.

12, 1993, "External Exposure to Radionuclides in Air, Water, and Soil."

EFPD shall be the ratio of the number of hours of production of a given THERMAL POWER to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, multiplied by the ratio of the given THERMAL POWER to the RTP.

One EFPD is equivalent to the thermal energy produced by operating the (continued)

Crystal River Unit 3 1.1-3 Amendment No.

RCS Specific Activity 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Specific Activity LCO 3.4.15 RCS DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits.

APPLICABILITY:

MODES 1, 2,

3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

DOSE EQUIVALENT 1-131 ---------

NOTE----------

not within limit.

LCO 3.0.4.c isý applicabl-e.

A.1

ýVerify DOSE' Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> EQUIVALENT 1-131 < 21 PCi/g.

AND A.2 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT 1-131 to within limit.

B.

DOSE EQUIVALENT NOTE-----------

XE-133 not within LCO 3.0.4.c is applicable.

limit.

B.1 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT XE-133 to within limit.

(conti nued)

Crystal River Unit 3 3.4-30 Amendment No.

RCS Specific Activity 3.4.15 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

Required Action and C.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A AND or B not met.

OR C.2 Be in MODE 5.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> DOSE EQUIVALENT 1-131

> 21 pCi/g.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 -------------------

NOTE ------------------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 7 days XE-133 specific activity < 646 pCi/g.

SR 3.4.1'5.2

NOTE------------------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 14 days 1-131 specific activity < 0.35 pCi/g.

AND Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after THERMAL POWER change of > 15%

RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period I

Crystal River Unit 3 3.4-31 Amendment No.

RCS Specific Activity 3.4.15 THIS PAGE INTENTIONALLY LEFT BLANK Crystal River Unit 3 3.4-32 Amendment No.

RCS Specific Activity 3.4.15 THIS PAGE INTENTIONALLY LEFT BLANK Crystal River Unit 3 3.4-33 Amendment No.

RCS Specific Acti vi ty B 3.4.15 B 3.4 REACTOR COOLANT SYSTEM (RCS)

B 3.4.15 RCS Specific Activity BASES BACKGROUND The maximum dose that an individual at the exclusion area boundary can receive for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> following an accident, or at the low population zone outer boundary for the radiological release duration, is specified in 10 CFR 50.67 (Ref. 1).

Doses to control room operators must be limited per GDC 19.

The limits on specific activity ensure that the offsite and control room doses are appropriately limited during analyzed transients and accidents.

The RCS specific activity LCO limits the allowable concentration level of radionuclides in the reactor coolant.

The LCO limits are established to minimize the dose consequences in the event of a steam line break (SLB) or steam generator tube rupture (SGTR) accident.

The LCO contains specific activity limits for both DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133.

The allowable levels are intended to ensure that offsite and control room doses meet the appropriate acceptance criteria in the Standard Review Plan (Ref. 2).

APPLICABLE SAFETY ANALYSES The LCO limits on the specific activity of the reactor coolant ensure that the resulting offsite and control room doses meet the appropriate SRP acceptance criteria following a SLB or SGTR accident.

The safety analyses (Refs.

3 and 4) assume the specific activity of the reactor coolant is at the LCO limits, and an existing reactor coolant steam generator (SG) tube leakage rate of 1.0 gpm exists.

The safety analyses assume the specific activity of the secondary coolant is at its limit of 4.5E-4 pCi/g DOSE EQUIVALENT 1-131 from LCO 3.7.16, "Secondary Specific Activity."

The analyses for the SLB and SGTR accidents establish the acceptance limits for RCS specific activity.

Reference to these analyses is used to assess changes to the unit that could affect RCS specific activity, as they relate to the acceptance limits.

(continued)

Crystal River Unit 3 B 3.4-71 Revision No.

RCS Specific Activity B 3.4.15 BASES APPLICABLE SAFETY ANALYSES (continued)

The safety analyses consider two cases of reactor coolant iodine specific activity.

One case assumes specific activity at 0.35 pCi/g DOSE EQUIVALENT 1-131 with a concurrent large iodine spike that increases the rate of release of iodine from the fuel rods containing cladding defects to the primary coolant immediately after a SLB (by a factor of 500), or SGTR (by a factor of 335),

respectively.

The second case assumes the initial reactor coolant iodine activity at 21.0 pCi/g DOSE EQUIVALENT 1-131 due to an iodine spike caused by a reactor or an RCS transient priorto the accident.

In both cases, the noble gas specific activity is assumed to be 646 pCi/g DOSE EQUIVALENT XE-133.

The SGTR analysis assumes a rise in pressure in the ruptured SG causes radioactively contaminated steam to discharge to the atmosphere through the atmospheric dump valves or the main steam safety valves.

The atmospheric discharge stops when the turbine bypass to the condenser removes the excess energy to rapidly reduce the RCS pressure and close the valves.

The unaffected SG removes core decay heat by venting steam until the cooldown ends and the Decay Heat Removal (DHR) system is placed in service.

The SLB radiological analysis. assumes that offsite power is lost at the same time as the pipe break occurs outside Containment.

The affected.SG blows down completely and steam is vented directly to the atmosphere.

The unaffected SG removes core decay heat iby venting steam to the atmosphereunt'il the cooldown:ends and the DHR system is placed in service.

Operation with iodine specific activity levels greater than the LCO limit is permissible, if the activity levels do not exceed 21.0 pCi/g for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

The limits on RCS specific activity are also used for establishing standardization in radiation shielding and plant personnel radiation protection practices.

RCS specific activity satisfies Criterion 2 of 10 CFR 50.36(c) (2) (ii).

LCO The iodine specific activity in the reactor coolant is limited to 0.35 pCi/g DOSE EQUIVALENT 1-131, and the noble gas specific activity in the reactor coolant is limited to 646 pCi/g DOSE EQUIVALENT XE-133.

The limits on specific activity ensure that offsite and control room doses will meet the appropriate SRP acceptance criteria (Ref.

2).

The SLB and SGTR accident analyses (Refs.

3 and 4) show (conti nued)

Crystal River Unit 3 B 3.4-72 Revision No.

RCS Specific Activity B 3.4.15 BASES LCO that the calculated doses are within acceptable limits.

(continued)

Violation of the LCO may result in reactor coolant radioactivity levels that could, in the event of a SLB or

SGTR, lead to doses that exceed the SRP acceptance criteria (Ref.

2).

APPLICABILITY In MODES 1, 2,

3, and 4, operation within the LCO limits for DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133 is necessary to limit the potential consequences of a SLB or SGTR to within the SRP acceptance criteria (Ref.

2).

In MODES 5 and 6, the steam generators are not being used for decay heat removal, the RCS and steam generators are depressurized, and primary to secondary leakage is minimal.

Therefore, the monitoring of RCS specific activity is not requi red.

ACTIONS A.1 and A.2 With the DOSE EQUIVALENT 1-131 greater than the LCO limit, samples at intervals of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> must be taken to demonstrate that the specific activity is

< 21.0 pCi/g.

The Completion Time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is required to obtain and analyze a sample.

Sampling is continued every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to provide a trend.

The DOSE EQUIVALENT 1-131 must be restored to within limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

The Completion Time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is acceptable since it is expected that, if there were an iodine spike, the normal coolant iodine concentration would be restored within this time period.

Also, there is a low probability of a SLB or SGTR occurring during this time period.

A Note permits the use of the provisions of LCO 3.0.4.c.

This allowance permits entry into the applicable MODE(S),

relying on Required Actions A.1 and A.2 while the DOSE EQUIVALENT 1-131 LCO limit is not met.

This allowance is acceptable due to the significant conservatism incorporated into the specific activity limit, the low probability of an event which is limiting due to exceeding this limit, and the ability to restore transient-specific activity excursions while the plant remains at, or proceeds to, power operation.

(continued)

Crystal River Unit 3 B 3.4-73 Revision No.

RCS Specific Activity B 3.4.15 BASES ACTIONS B.1 (continued)

With the DOSE EQUIVALENT XE-133 greater than the LCO limit, DOSE EQUIVALENT XE-133 must be restored to within limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

The allowed Completion Time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is acceptable since it is expected that, if there were a noble gas spike, the normal coolant noble gas concentration would be restored within this time period.

Also, there is a low probability of a SLB or SGTR occurring during this time period.

A Note permits the use of the provisions of LCO 3.0.4.c.

This allowance permits entry into the applicable MODES(S),

relying on Required Action B.1 while the DOSE EQUIVALENT XE-133 LCO limit is not met.

This allowance is acceptable due to the significant conservatism incorporated into the specific activity limit, the low probability of an event which is limiting due to exceeding this limit, and the ability to restore transient-specific activity excursions while the plant remains at, or proceeds to, power operation.

C.1 and C.2 If the Required Action and associated Completion Time of Condition A or B is not met, or if the DOSE EQUIVALENT 1-131 is

> 21.0 pCi/g, the reactor must be brought to MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.4.15.1 REQUIREMENTS SR 3.4.15.1 requires performing a gamma isotopic analysis as a measure of the noble gas specific activity of the reactor coolant at least once every 7 days.

This measurement is the sum of the degassed gamma activities and the gaseous gamma activities in the sample taken.

This Surveillance provides an indication of any increase in the noble gas specific activity.

(continued)

Crystal River Unit 3 B 3.4-74 Revision No.

RCS Specific Activity B 3.4.15 BASES SURVEILLANCE SR 3.4.15.1 (continued)

REQUIREMENTS Trending the results of this Surveillance allows proper remedial action to be taken before reaching the LCO limit under normal operating conditions.

The 7 day Frequency considers the low probability of a gross fuel failure during this time.

Due to the inherent difficulty in detecting Kr-85 in a reactor coolant sample due to masking from radioisotopes with similar decay energies, such as F-18 and 1-134, it is acceptable to include the minimum detectable activity for Kr-85 in the SR 3.4.15.1 calculation.

If a specific noble gas nuclide listed in the definition of DOSE EQUIVALENT XE-133 is not detected, it should be assumed to be present at the minimum detectable activity.

A Note modifies the SR to allow entry into and operation in MODE 4, MODE 3, and MODE 2 prior to performing the SR.

This allows the Surveillance to be performed in those MODES, prior to entering MODE 1.

SR 3.4.15.2 This Surveillance is performed to ensure iodine specific activity remains within the LCO limit during normal operation and following fast power changes when iodine spiking is more apt to occur.

The 14 day Frequency is adequate to trend changes in the iodine activity level, considering noble gas activity is monitored every 7 days.

The Frequency, between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a power change

> 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, is established because the iodine levels peak during this time following iodine spike initiation; samples at other times would provide inaccurate results.

The Note modifies this SR to allow entry into and operation in MODE 4, MODE 3, and MODE 2 prior to performing the SR.

This allows the Surveillance to be performed in those

MODES, prior to entering MODE 1.

(continued)

Crystal River Unit 3 B 3.4-75 Revision No.

RCS Specific Acti vi ty B 3.4.15 BASES REFERENCES

1.

10 CFR 50.67.

2.

Standard Review Plan Section 15.0.1, "Radiological Consequence Analyses Using Alternative Source Terms."

3.

FSAR Section 14.2.2.1, "Steam Line Failure Accident."

4.

FSAR Section 14.2.2.2, "Steam Generator Tube Rupture Accident."

Crystal River Unit 3 B 3.4-76 Revision No.

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