ML20198H373

Amend 202 to License DPR-70,increasing Allowable Band for Control & Shutdown Rod Demanded Position Versus Indicated Position from +12 Steps to +18 Steps When Power Level Not Greater That 85% Rated Thermal Power

ML20198H373
Person / Time
Site:	Salem
Issue date:	12/22/1997
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Public Service Electric & Gas Co, Philadelphia Electric Co, Delmarva Power & Light Co, Atlantic City Electric Co
Shared Package
ML20198H378	List: ML20198H373 ML20198H389
References
DPR-70-A-202 NUDOCS 9801130269
Download: ML20198H373 (9)

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UNITED STATES p-NUCLEAR REGULATORY COMMISSION WASHINOf oN D.C. 30MH001 s,e see*

PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY QELMAP.VA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTEIC. COMPANY DQCKET NO. 50-271 SALEN NUCLEAR GENERATING STATION. UNIT NO. I N D DMENT TO FACILITY OPERATING LICENSE Amendment No.202 License No. DPR-70 1.

The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A.

The application for amendment flied by the Public Service Electric &

Gas Company, Fhiladelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated October 6,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance:

i) that the activities authorized by this amendment can be conducted (without endangering the health and C.

that such activities will be conducted safety of the public, and (ii) ion's regulations set forth in 10 CFR in compliance with the Commiss Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:

$I D b O N$$$72 P

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! i (2) Technical Snacifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B as revised through Amendment No. 202 e areherebyincorporatedInthe Itcense. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance, to be implemented within 60 days.

FOR THE NUCLEAR R GULATORY COMIS$10N s

nF.Stolz,Direc1or Project Directorat M -2 Division of Reactor Projects - 1/l!

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

De: caber 22, 1997 nn--.

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ATTACMENT 10 LICENSE AMENDMENT NO. 202 EACILITY OPERATING LICENSE NO. DPR-70 DOCK [T NO. 50-272 Revise Appendix A as follows:

Renova._Pages Insert Paans 3/4 1-18 3/4 1-18 3/4 1-18a 3/4 1-18a 3/4 1-19 3/4 1-19 3/4 1-19a 3/4 1-19a B 3/4 1-4 8 3/4 1-4 8 3/4 2-4 8 3/4 2-4 l

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b maacriviry conrrant avaruus 1/a.i.1 neoVARLs c0AfTROL AAAmbed.IEa anoce uniaarr LIMITING CONDITION POR OPERATION 3.1.3.1 All full length (shutdown and control) rods, shall be OPERABLE and positioned within i 18 8tePs (indicated position) when reactor power is s 85%

RATED THERMAL POWER,. or i 12 steps.(indicated position) when reactor power is

> 85% RATED THERMAL POWER, of their group step counter demand position within one hour after rod motion.

APPLICAEILITY: MODES 1* and 2*

I Action:

a.

With one or more full length rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in NOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

With me,re than one full length rod inoperable or mis aligned from the group step counter demand position by more than 2 18 steps (indicated position) at 5 85% RATED THERMAL POWER or i 12 steps (indicated position) at > 85% RATED THERMAL POWER, be in NOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

c.

With one full length rod ineperable due to causes other than addressed by ACTION a, above, or mis-aligned from its group step counter demand position by more than i 18 steps (indicated position) at 5 85% RATED THERMAL POWER or i 12 steps (indicated position) at > 85% RATED THERMAL POWER, POWER OPERATION may continue provided that within one hour either:

l 1.

The rod is restored to OPERABLE status within the above alignment requirements, or 2.

The remainder of the rods in the bank with tha inoperable rod are aligned to within t 18 steps (indicated position) at 5 85% RATED THERMAL POWER or i 12 steps (indicatec'. positiot.)

at >85% RATED THERMAL POWER, of the inoperable rod while maintaining the rod sequence and insertion limits of Figures 3.1-1 and 3.1-2; the THERMAL POWER level shall-be restricted

. pursuant to Specification 3.1.3.5 during subsequent operation,- or 3..

The rod is' declared inoperable and the SHUTDCWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

POWER OPERATION may.then continue provided thats l-

• See Special Test Exceptions 3.10.2 and 3.10.3.

SALEM - UNIT 1 3/4 1-18

~ Amendment No. 202

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a)

A reevaluation of each accident analysis of Table 3.1-1 is perforned within 5 days; this reevaluation shall confirm that the previously.

analyced results of these accidents remain valid for the duration of operation under these conditions, b)

The SHUTDOWW MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, c)

A power distribution map is obtained from the movable incore detect 6ru and Fe !Z) and f g are verified to be within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

d)

The THERMAL POWER level is reduced to less than or equal to 75% of RATED TMERMAL POWER within one hour and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER. THERMAL POWER shall be maintained less than or equal to 75% of RATED THERMAL POWER until compliance with ACTIONS 3.1.3.1.c.3 a and 3.1.3.1.c.3.c above are demonstrated.

SURVRILLANCE REQUIREMENTS

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4.1 3.1.1 The position of each full length rod shall be determined to be wititin the limits established in the limiting condition for operation at least once per 12 houts (allowing for one hour thermal soak af ter rod motion) except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4.1.3.1.2 Each full length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 31 days.

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i SALEM - UNIT 1 3/4 1-18a Amendment No. 202 l

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f-i anacTivrTY coarrant aYarness 90EITICAf IMDicAT100f aYSTEME - OPERATIMG LIMITING COIEDITIOtt FOR OPERATION 2.1.3.2.1. The shutdown and control rod position indication systems shall be OPERABLE and capable of determinirg the actual and demanded rod positions as followsE j

a.-

Analog rod position indicators, within one hour after rod motion (allowsuce for thermal soak);

j All shutdown Rankm: 1 it steps at 505% reactor power or if reactor power is > 954 RATED THERMAL POWER 1 12 steps of the group demand counters for withdrawal ranges of 0-30 steps and 200-22e steps.

enntral Rank As i le steps at 5854 reactor power or if reactor power is

> 85% RATED THERMAL POWER t 12 steps of the group demand counters for withdrawal ranges of 0-30 steps and 200-228 steps.

l control mank me i 18 steps at 505% reactor power or if reactor power is

> 05% RATED THERMAL POWER t 12 steps of the group demand counters for withdrawal ranges of o-30 steps and 150-228 steps, i

taneral mank. c and D: 1 it steps at 545% reactor power or if reactor power is > 85% RATED THERMAL POWER t 12 steps ot' the group demand counters for withdrawal range of 0-228 steps, i

b..

Group demand counteral i 2 steps of the pulsed output of the Slave cycler Circuit over the withdrawal range of 0-228 steps.

1 APPLICARILITY: MODES 1 and 2.

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i a.

With a maximum of one analog rod position indicator per bank.

inoperable either:

1. Determine the position of the non-indicating rod (s) indirectly by the movable incore detectors at least once per a hours and h

within one hour after any motion of the non-indicating rod which exceods 24 steps in.one direction since-the last determination of the rod's position, or

3. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

b...With two or more analog rod position indicators per bank inoperable, within one hour restore-the inoperable rod position indicator (s)'to ll OPERABLE status or be in NOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. A 3

j.

. maximum of one rod position indicator per bank may remain inoperable ifo11owing the hour, with Action (a) above being applicable from *.he original entry tie.a into the Leo.

SALEM - UNIT 1-3/4 1-19

' Amendment No.202 l 1

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c.

With a maximum of one group demand position indicator per bank inoperable either:

1.

Verify that all analog rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of 18 steps when reactor power is 5 85% RATED THERMAL POWER or if reactor power is > 85% RATED THERMAL POWER, 12 steps of each i

other at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or 1

2.

-Reduce THERMAL POWER to less than 50% of RATED THERMAL POWhA within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

I SURVEILLANCE REQUIREMENTS 4.1.3.2.1.1 Each analog rod position indicator shall be determined to be OPERABLE by verifying that the demand position indication system and the rod position indication system agree within 18 steps when reactor power is s 85%

RATED THERMAL POWER or if reactor power is > 85% RATED THERMAL POWER, 12 steps (allowing for one hour thermal soak af ter rod motion) at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then compare the demand position indication system and the rod position indication system at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

i 4.1.3.2.1.2 Each of the above required rod position indicator (s) shall be determined to be OPERABLE by, performance of a CHAf*NEL calibration at least once per 18 months.

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l SALEM - UNIT 1'

.3/4 1-19a Amendment No. 202

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)tEACTIVITY CONTROL SYSTEMS BASES The boron capability required below 200'F is suf ficient to provide a SHUTDOWN MARGIN of 1% delth k/k af ter xenon decay and cooldown f rom 200'F to 14 0'F. This condition requires either 2,600 gallons of 6,560 ppm borated water from the boric acid storage tanks or 7,100 gallons of 2,300 pom borated water from the refueling water storage tank.

The 37,000 gallons limit in the refueling water storage tank for Modes 6 and 6 is based upon 21,210 gallons that is undetectable due to lower tap location, 8,550 gallons for instrument error, 7,100 gallons required for shutdown margin, and an additional 140 gallons due to rounding up.

The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components. The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics, 4te OPERABILITY of one boron injection system during REFUELING ensures that this system is available for reactivity control while in MODE 6.

3 /4.L 2 MovAntv c0NTROL ASSEMBLYES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) limit th6 potential effects of rod mis-alignment on associated accident analyses. OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits. OPERABLE condition for the analog rod position indicators is defined as being capable of indicating rod position to within the allowed rod misalignment relative to the bank demand position for a range of positions. For the Shutdown Banks, and control Bank A this range is defined as the group demand countet indicated position between 0 and 30 steps withdrawn inclusive, and between 200 and 228 steps withdrawn inclusive.

This permits the operator to verify that the control rods in these banks are either fully withdrawn or fully inserted, the normal operating modes for these banks.

Knowledge of these banks positions in these ranges satisfies all accident analysis assumptions concerning their k

position. The range for control Bank B is defined as the group demand counter indicated position between 0 and 30 steps withdrawn inclusive, and between 160 and 228 steps withdrawn inclusive.

For Control Banks C and D the ranga is defined as the group demand counter indicated position between 0 and 228 steps withdrawn. Comparison of the group demand counters to the bank insertion limits with verification of rod position with the analog rod position indicators (af ter thermal soak af ter rod motion) is sufficient verification that the con rol rods are above the insertion limits. The full out position will be specifically established for each cycle by the Reload Safety Analysis for that cycle. This position will be within the band established by " FULL WITHDRAWN" and will be administrative 1y controlled. This band is allowable to minimize RCCA wear, pursuant to Information Notice 87-19.

20.J SALEM - UNIT 1 B 3/4 1-4 Amendment No.

POWER DISTRIBUTION LIMITa BASES e n s e m e s m o s o m a s s e s s e s s e s s m e e s s a m m e n e s s m e n e m m e n e s a m m e n s e s s e s s e n e e s e s e n e s s m e s e s s e.

3/4.2.2 a m4 3/4.2.3 IfEAT FLUX AlTD NUC' LEAR EliT11ALPY 11OT (*1tAffffEL AND RADIAL PEAYYNG PACTOPJ!1 -

r, f z) ttm P',

The limits on heat flux and nuclear enthalpy hot channel f actors and RCS flaw rate ensure that 1) the design limits on peak local power density and minimum DNBR are not exceeded and 2) in the event of a LOCA the peak fuel clad temperature will not exceed the 3200'F ECCS acceptance criteria limit.

Each of these hot channel factors are measurable but will normally only be determined periodically as specified in specifications 4.2.2 and 4.2.3.

This periodic surveillance is sufficient to insure that the limits are maintained provided-a.

Control rod in a single group move together with no individual rod insertion differing from the group demand position by more than the allowed rod misalignment.

b.

Control rod groups are sequenced with overlapping groups as described in specification 3.1.3.5.

c.

The control rod insertion limits of specifications 3.1.3.4 and 3.1.3.5 are maintained.

d.

The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits.

The relaxation in fa as a function of THERMAL POWER allows changes in the radial power shape for all permissible rod insertion limits.

fu will be maintained within ite limits provided condi.iono a through d above, are maintained.

When an Fg measureeent is taken, both experimental error and manufacturing tolerance must be allowed for.

Five percent is the appropriate allowance for a full core map taken with the incore detector flux mapping system and 3% is tho appropriate allowance for manufacturing tolerance.

When fu is measured, experimental error must be allowed for and 4% is the appropriate allowance for a full core map taken with the incore detection system.

The specified limit for fu also contains an 8% allowance for uncertainties which mean that normal operation will result in fa 51.55/1.08.

The et allowance is based on the following considerations:

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SALEM - UNIT 1 B 3/4 2-4 Amendment No.

202

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