ML20087J807

Proposed Tech Specs Moving Overtemp N-16 Limits to COLR

ML20087J807
Person / Time
Site:	Comanche Peak
Issue date:	08/15/1995
From:	TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20087J795	List: ML20087J792 ML20087J807
References
NUDOCS 9508220179
Download: ML20087J807 (72)

Text

. . _ .. . . .

.-_ ':__.:4_.-

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mm ; -

O ;y; 7 _

gy' TABLE 2.2-1

a 4

Q$ REACTOR TRIP SYSTEN' INSTRUMENTATION TRIP SETPOINTS l 8;$ -

88

, Jgg ; FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE ,

x,

" 1. Manual Reactor Trip N.A.

i-

.N.A -.

! 2. Power Range, Neutron Flux -

a. High Setpoint $109% of RTP* $111.7% of RTP* l

b. Low Setpoint s25% of RTP* s27.7 of RTP*

, 3. Power Range, Neutron Flux, s5% of.RTP* with- $6.3% of RTP* with

'High Positive Rate a time constant a time constant 22 seconds 22 seconds ,

4. Not Used '.

5. Intermediate Range, 525% of RTP* $31.5 of RTP*

Neutron Flux l

6. Source Range, Neutron Flux s105 cps sl.4 x 10 cps 5

_S -

A ,

7. Overtemperature N-16 C.. .. a WW .pt #  :

't i

• RTP-- RATED THERMAL POWER W91E As seme@eA in %e.L Cate. o(*<< Mag um*5 T'Po*(

2. '

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COMANCHE PEAK - UNIT 1 AND 2 2-5 Unit 11 Amendment No. 2,14,21,3",41 Unit 2 - Amendment No. h 46,27

_ _ _ _ _ _ _ _ _ _ _ ____________________._..._...a.__.-.._ _ . - . _ _ _ . . . _ _ _ _ _ _ . _ . . - _ . . . . . . . _ _ _ _ . _ _ . . .......__ _ -

s 3;

n Q/

/

TABLE 2.2-1 ' Continued) y Autt no A' IONS -

fNOTE 1: Over n

M erature N-16 h N =. Ki -K '

T,-T,*]

x 2[1+rs a K3 (P-P') '- f, (aq) .

E M.

v iPiere: N Measured M-16 Powe by ion chambers, -l

~ f

{ T, -

Cold leg temper ure, *F, E

.9 ,

=

560.5*F.for I it 1, 560.3*F for Unit 2 ;<[ Reference T, at RATED T K, - 1.150, K, =

0.0134 F for Unit 1 0.018456/*F for Unit 2 ,

1 t_I 1 - T function generated by the lead-lag controller for

^

1+rsa , dynamic compensation, 7 3 , r, ' Time constants utilizeWin the lead-lag controller for T,, r, ;t 10 s, and 7 2 3 s, K3 = 0.000719/psig for it I cc 0.000898/psig fo Unit 2 i

,,c.

~, , De.\e.Te.

aa

TA8LE 2.2-1 (Continuetil TABLENOTATIONS(Continued /

.g f

= NOTE (Continued) '

9 7 P - Pressurizer pressure, ig, -

' 2 2235 psig (Nominal S operating pressure),

LE ,

--e

[ S - Laplace transf operator, s,

E and f aq is a function the indicated difference bet top and bottom halves of deteck(ors)of the power-nge neutron ion chambers; with ins to be selected based on measured instrument ponse during plant STARTUP test such that:

For Unit 1 .

i (1) for ED q,THE between l POWER-65% in theand top an(4ottom+4%, f,(4q) halves - 0, of where t q,he core respectivand y, g 7 nd q, + g is total THElWIAL in percent of RATED THElWWW. POWER o

(11) for each percent that the itude of q - g exceeds -65%, the -16 Trip Setpoint shall be automat allyreducedby1.81%ofitsvalue RATED THElWIAL POWER, and cc 11 -(iii) for each percent th the magnitude of q - q exceeds , the N-16 Trip Setpoint shall be utomatically reduced by 2.u26% of i value at RATED

(( THERMAL POWER.

De.\e-te ll

(

an E..E i3 r

s~

_ _ _ _ _ _ _ - . , . _ _ _ __ _. -- -. .. .. . ._m __

1 s

TELE 2.2-1 (Continued)

TABL E N0"A" IONS (ConMnued) .

NOTE 1: (Continued)

For it 2 ,

(' ) for q - gebetween -5 and +5.5%, f (aq) - 0, where q nd q are percent RATED, THERMAL POWER,M the top and bo,ttom halves of the core ,respectively, and q, + q, is t THERMAL POWER in percent of ED THERMAL POWER, .

(11) for each percent that the magnitude of q - q, exceeds -52%, ' the N-16 Trip Setpoint shall be automatically reduced by 2J5% of its value at RATED THERMAL POWER, (iii) exceeds +5.5%, the N-16 Trip forjech S percent that the magnitude off - q,7% of its value at RATED THERMAL ointshallbeautomaticallyredu(dby2.1 ER.

l MTE 2: The chan 's maximum Trip Setpoint shall n exceed its computed Trip Setpoint by e t6an 3.51%L of spa or Unit 1 or 2.85% of span for UM 2. l COMANCHE PEAK - UNIT I AND 2 2-11' Unit.1 - Amendment No. 4hM,41

. Uni t 2 - Amendment No. 7, 27 .

a _ _ _ _ _ . . _ _ _ _ _ . _ - . . . _ . . . _ _ .. _ __

A[MINISTRATIVE CONTROLS

)

MONTHLY OPERATING REPORTS (Continued)  !

shall'be submitted on a monthly basis to'the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555, with-a copy to the l Regional Administrator of the Regional Office of the NRC, no later than the g..

15th of each month _ following the calendar month covered by the report.

g (* CORE OPERATING LIMITS REPORT

.. s C 6.9.1.6a Core operati g 't,- limits shall be established and documented in the CORE OPERATING LIMITS R PORT (COLR) before each reload cycle or any remaining

,, o paet of.a reload cycle for the following:.

T5 at -

1). Moderator temperature coefficient 80L and EOL limits and 300 ppe sur-g .$ veillance limit for Specification 3/4.1.1.3,  ;

gh 2). Shutdown Rod Insertion Limit for Specification 3/4.1.3.5,

$p 3). Control Rod Insertion Limits for Specification 3/4.1.3.6, y

January 1989. OS

a_ 11). RXE-88-102-P, Sup. 1, "TUE-1 DN8 Correlation - Supplement 1",

es g December 1990. cv (-.

12) RXE-89-002, "VIPRE-01 Core Thermal-Hydraulic Analysis Methods for d Comanche Peak Steam Electric Station Licensing Applications", June g 1989. ~ 1 l

13). RXE-91-001, " Transient Analysis Methods for Comanche Peak Steam Electric Station Licensing Applications", February 1991. 14). RXE-91-002, " Reactivity Anomaly Events Methodology", May 1991. (Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient 3.1.3.5 - Shutdown Bank Insertion Limit. 3.1.3.6 - ' Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.) 15). RXE-90-007, "Large Break Loss of Coolant Accident Analysis Methodology" December 1990. 16). TXX-88306, " Steam Generator Tube Rupture Analysis", March 15, 1988. 17). RXE-91-005, " Methodology for Reactor Core Response to Steamline Sreak Events," May, 1991. s i COMANCHE PEAK - UNITS 1 AND 2 6-21 Unit 1 - Amendment No. 1,0,10,10,21,2",34 Unit 2 - Amendment No. i,7,10.20 1 i ENCLOSURE 1 TO TXX 95214 GENERIC LETTER 88-16 P.EH0 VAL OF CYCLE SPECIFIC PARAMETER LIMITS FROM TECHNICAL SPECIFICATIONS [ i ,.. .. l / %g UNITED STATES !"' o NUCLEAR REGULATORY COMMISSION { ji wAsmwoTow,s. c.2oses ...../ OCT 0 4 m TO ALL POWER REACTOR LICENSEES AND APPLICANTS l

SUBJECT:

REMOVAL OF CYCLE-SPECIFIC PARAMETER LIMITS FROM TECHNICAL ,

SPECIFICATIONS (GENERIC LETTER 88-16) '

License amendments are generally required each fuel cycle to update the values of cycle-specific parameter limits in Technical Specifications (TS). The processing of changes to TS that are developed using an NRC-approved method-ology is an unnecessary burden on licensee and NRC resources. A lead plant proposal for an alternative that eliminates the need for a license amendment to update the cycle-specific parameter limits each fuel cycle was submitted for the Oconee plant with the endorsement of the Babcock and Wilcox Owners Group. On the basis of the NRC review and approval of that proposal, the en-closed guidance for the preparation of a license amendment request for this alternative was developed by the NRC staff.

Generally, the methodology for determining cycle-specific parameter limits is documented in an NRC-approved Topical Report or in a plant-specific submittal.

As a consequence, the NRC review of proposed changes to TS for these limits is primarily limited to confirmation that the updated limits are calculated using an NRC-approved methodology and consistent with all applicable i;mits of the safety analysis. These changes also allow the NRC staff to trend the values of these limits relative to past experience. This alternative allows continued trending of these limits without the necessity of prior NRC review and approval, i Licensees and applicants are encouraged to propose changes to TS that are consistent with the guidance provided in the enclosure. Conforming amendments will be expeditiously reviewed by the NRC Project Manager for the facility.

Proposed amendments that deviate from this guidance will require a longer, more detailed review. Please contact the Project Manager if you have questions on this matter.

Sincerely, 8810050058

'p Dennis M. Crutchfiel Acting Associate Di ector for Projects RECE D Office of Nuclear Reactor Regulation i

Enclosure:

As stated OCT 211988 l WILLIAM G. COUNSIL 7son i, nl wwcw, &, pg2 1';lA, @ Sfp v

g_

s .

i i

Generic Letter 88- 16 Enclosure I GUIDANCE FOR TECHNICAL SPECIFICATION CHANGES FOR CYCLE-SPECIFIC PARAMETER LIMITS INTRODUCTION A number of Technical Specifications (TS) address limits associated with

reactor physics parameters that generally change with each reload core, requir-ing the processing of changes to TS to update these limits each fuel cycle.

If these limits-are developed using an NRC-approved methodology, the license ,

amendment process is an unnecessary burden on the licensee and the NRC. An alternative to including the values of these cycle-specific parameters in in-dividual specifications is provided and is responsive to industry and NRC efforts on improvements in TS.

This enclosure provides guidance for the preparation of a license amendment  :

request to modify TS that have cycle-specific parameter limits. An acceptable alternative to specifying the values of cycle-specific parameter limits in TS '

was developed on the basis of the review and approval of a lead p' lant proposal for this change to the TS for the Oconee units. The implementation of this alternative will result in a resource savings for the licensees and the NRC by eliminating the majority of license amendment requests on changes in values of cycle-specific parameters in TS.

DISCUSSION This alternative consists of three separate actions to modify the plant's TS:.

(1) the addition of the definition of a named formal report that includes the values of cycle-specific parameter limits that have been established using an NRC-approved methodology and consistent with all applicable limits of the safe-ty analysis, (2) the addition of an administrative reporting requirement to sub-mit the formal report on cycle-specific parameter limits to the Commission for information, and (3) the modification of individual TS to note that cycle-specific parameters shall be maintained within the limits provided in the defined formal' report.

In the evaluation of this alternative, the NRC staff concluded that it is essential to safety that the plant is operated within the bounds of cycle-specific parameter limits and that a requirement to maintain the plant within the appropriate bounds must be retained in the TS. However, the specific

• values of these limits may be modified by licensees, without affecting nuclear safety, provided that these changes are determined using an NRC-approved method-ology and consistent with all applicable limits of the plant safety analysis that are addressed in the Final Safety Analysis Report (FSAR). Additionally, it was concluded that a formal report should be submitted to NRC with the values of these limits. This will allow continued trending of this information, .

even though prior NRC approval of the changes to these limits would not be required.

The current method of controlling reactor physics parameters to assure conform-ance to 10 CFR 50.36 is to specify the specific value(s) determined to be with-in specified acceptance criteria (usually the limits of the safety analyses) using an approved calculation methodology. The alternative contained in this .

guidance controls the values of cycle-specific parameters and assures conform- '

ance to 10 CFR 50.36, which calls for specifying the lowest functional f

F

1 Generic tetter' 88- 16 Enclosure p

' erformance levels acceptable for continued safe operation, by specifying the calculation methodology and acceptance criteria. This permits operation at any specific value determined by the licensee, using the specified methodology, to be within the acceptance criteria. The Core Operating Limits Report will docu-ment the specific values of parameter limits resulting from licensee's calcula-tions including any mid-cycle revisions to such parameter values.

The following items show the changes to the TS for this alternative. A defined formal report, " Core Operating Limits Report" (the name used as an example for the title for this report), shall be added to the Definitions section of the TS, as follows.

[ CORE] OPERATING LIMITS REPORT

1. X X The [ CORE] OPERATING LIMITS REPORT is the unit-specific document that provides [ core] operating limits for the current operating reload cycle. These cycle-specific [ core] operating limits shall be determined for each reload cycle in accordance with Specification 6.9.X. Plant operation within these operating limits is addressed in individual specifications.

A new administrative reporting requirement shall be added to existing reporting requirements, as follows.

CORE] OPERATING LIMITS REPORT

6. 9. X] [ Core] operating limits shall be established and documented in the

[ CORE] OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle. (If desired, the individual specifications that address [ core] operating limits may be referenced.) The analytical methods used to determine the [ core] operating limits shall be those previously re-viewed and approved by NRC in [ identify the Topical Report (s) by number, title, and date, or identify the staff's safety evaluation report for a plant-specific methodology by NRC letter and date). The [ core] operating limits shall be determined so that all applicable limits (e.g., fuel therm-al-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. The [ CORE] OPERATING LIMITS REPORT, in-cluding any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

Individual specifications shall be revised to state that the values of cycle-specific parameters shall be maintained within the limits identified in the defined formal report. Typical modifications for individual specifications are as follows.

The regulating rods shall be positioned within the acceptable operatin range for regulating rod position provided in the [ CORE] OPERATIN TS REPORT. (Used where the operating limit covers a range of acceptable operation, typically defined by a curve.)

The [ cycle-specific parameter) shall be within the limit provided in the

[ CORE] OPERATING LIMITS REPORT. (Used where the operating limit has a single point value.)

. ' Generic Letter 88- 16 Enclosure i

SUMMARY

The alternative to including the values of cycle specific parameter limits in individual specifications includes (1) the addition of a new defined term for the formal report that provides the cycle-specific parameter limits, (2) the addition of its associated reporting requirement to the Administrative Controls section of the TS, and (3) the modification of individual specifications to re-place these limits with a reference to the defined formal report for the values of these limits. With this alternative, reload license amendments for the sole purpose of updating cycle-specific parameter limits will be unnecessary.

e- -

~

Enclosure LIST OF RECENTLY ISSUED GENERIC LETTERS Generic Date of Letter No. Eubject Issuance Issued To 88-15 ELECTRIC POWER SYSTEMS - 09/12/88 ALL POWER REACTOR INADEQUATE CONTROL OVER LICENSEES AND '

DESIGN PROCESSES APPLICANTS ~

88-14 INSTRUMENT AIR SUPPLY 08/08/88 ALL HOLDERS OF SYSTEM PROBLEMS AFFECTING OPERATING LICENSES SAFETY-RELATED EQUIPMENT OR CONSTRUCTION PERMITS FOR NUCLEAR  !

POWER REACTORS l 88-13 OPERATOR LICENSING 08/08/88 ALL POWER REACTOR EXAMINATIONS LICENSEES AND APPLICANTS FOR ,

AN OPERATING LICENSE.

88-12 REMOVAL OF FIRE PROTECTION 08/02/88 ALL POWER REACTOR REQUIREMENTS FROM TECHNICAL LICENSEES AND SPECIFICATIONS APPLICANTS 88-11 NRC POSITION ON RADIATION 07/12/88 ALL LICENSEES OF EMBRITTLEMENT OF REACTOR OPERATING REACTORS VESSEL MATERIALS AND ITS AND HOLDERS OF IMPACT ON PLANT OPERATIONS CONSTRUCTION PERMITS 88-10 PURCHASE OF GSA APPROVED 07/01/88 ALL POWER REACTOR SECURITY CONTAINERS LICENSEES AND HOLDERS OF PART 95-APPROVALS 88-09 PILOT TESTING 0F FUNDAMENTALS 05/17/88 ALL LICENSEES OF ALL EXAMINATION BOILING WATER REACTORS AND APPLICANTS FOR A BOILING WATER REACTOR OPERATOR'S LICENSE UNDER 10 CFR PART 55 88-08 MAIL SENT OR DELIVERED TO 05/03/88 ALL LICENSEES FOR POWER THE OFFICE OF NUCLEAR REACTOR AND NON-POWER REACTORS REGULATION AND HOLDERS OF CONSTRUCTION PERMITS FOR NUCLEAR POWER REACTORS 88-07 MODIFIED ENFORCEMENT POLICY 04/07/88 ALL POWER REACTOR RELATING TO 10 CFR 50.49, LICENSEES AND

" ENVIRONMENTAL QUALIFICATION APPLICANTS OF ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY FOR NUCLEAR POWER PLANTS" a