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Amend 162 to License NPF-3,revising Control Rod Assembly Position Indication Acceptance Criteria & Making Administrative Corrections
	ML20082Q647
Person / Time
Site:	Davis Besse
Issue date:	09/04/1991
From:	Hopkins J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20082Q650	List: ML20082Q647; ML20082Q651;
References
	NUDOCS 9109130016
	Download: ML20082Q647 (12)
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s i 'n UNITED STATES i.-),~f 7// [E NUCLEAR REGULATORY COMMISSION WASHINGTON, D C. 20t46 s,,

n : y TOLEDO EDISON COMPANY CENTER 10R SERVICE COMPANY 0.Np THE Cl @ LAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. $0-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDHENT TO FACILITY OPERATING LICENSE Amendment No. 162 License No. NPF-3 1.

The Nuclear Regulatory Commission (the Commission) has fc,und that:

A.

The application for amendment by the Toledo Edison Company, Centerior Service Company, and the Cleveland Electric 111uminating Company (the licensees) dated February 1, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

end the Comm'ssion'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; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without cndangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the heiith 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 it amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF.3 is hereby anended to read as follows:

l 9109130016 910904 PDR ADOCK 0b000346 l

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(a) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.162, are hereby incorporated in the license.

The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications, 3.

This license amendment is effective as of its date of issuance and shall be impicmented not later than 45 days af ter issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 9

Jon B. Hopkins, Sr. Project Manager Project Directorate 111 3 Division of Reactor Projects !!!/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

Seotember 4, 1991

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ATTACHMENT TO LICENSE AMENDMENT NO.16?

FACILITY OPERATING LICENSE NO._NPF-3 DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment nunber and i

contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Remove Insert 3/4 1-20 3/4 1-20 3/4 1-21 3/4 1-21 3/4 1-22 3/4 1-22 3/4 1-23 3/4 1-23 B 3/4 1-4 B 3/4 1-4 B 3/4 1-5 E

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REACTIVITY CONTROL SYSTEMS 3/4.1.3 tiOVABLE CONTROL ASSEMBLIES GROUP _HElGHT - SAFETY AND REGULATING ROD GROUPS l

LIMITING CONDITION FOR OPERATIONS 3.1.3.1 All control (safety and regulating) rods shall be OPERABLE and positioned within 1 6.5% (iridicated position) of their group average height.

APPLICABillTY: MODES l' and 2*.

ACTION:

a.

With one or more control rods inoperable due to being innovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN KARGIN requirement of Specification 3.1.1.1 is satisfied wittiin one hour and be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With more than one control rod inoperable or misaligned from its group average height by core than + 6.5% (indicated position), be in at least HOT STANDBY within 6 houre, c.

With one control rod inoperable due to causes other than addressed by ACTION a, above, or misaligned from its group average height by more than + 6.5% (indicated position), POWER OPERATION may continue provided that within one hour either:

1.

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

The control rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue provided that; a)

.An analysir "f the potential ejected rvo worth is performed within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and the rod worth is deter-mined to be < 1.0% ok at zero power and < 0.65t ok at RATED THERKAL POWER for the remainFer of the fuel cycle.

b)

The SHUTDOWN KARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

5ee Special Test Exceptions 3.10.1 and 3.10.2.

DAVIS-BESSE, UNIT 1 3/4 1-19 r

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REACTIVITY CONTROL SYSTEMS GROUP HEIGHT - SAFETY AND REGULATING ROD GROUPS LIMITING _ CONDITION FOR OPERATIONS ACTION:

(Continued) c)

Apowerdistributionmqpisobtainedfromtheincere detectors and Fg and F'H are verified to be within their limitswithin7choursg d)

Either the THERMAL POWER level is reduced to < 60% of the THERMAL POWER allowable for the reactor ciolent pump combination within one hour and within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the High Flux Trip Setpoint is reduced to < 70% of the THERMAL POWER allowable for the reactor coolant pump combination, or e)

The remainder of the rods in the group with the inoperable rod are aligned to within 1 6.5% of the inoperable rod within one hour while maintaining the position of the rods within the limits provided in the C0'tE OPERATING LIMITS REPORT; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation.

SURVE!LLANCE REQUIREMENTS 4.).3.1.1 The position of each cct. trol rod shall be determined to be within the group average height limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the asymmetric rod monitor is inoperable, then verify the individual rod position (s) of the rod (s), with the inoperable asymmetric rod monitor at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Each control rod not fully inserted shall be determined to be OPERABLE by moyament of at least 2% in any one direction at least once ever' 31 days.

DAVIS-BESSE, UNIT 1 3/4 1-20 Amendment No. UE,AA4/.162

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RE AC11vlTY CONTROL SYSTEMS GROUP HEIGHT - AXI AL_ POWER SHAPING ROD GROUP _

l LIMITING CONDITION FOR OPERATION f

3.1.3.2 All axial power shaping rods (APSR) shall be OPERABLE, unless fully withdrawn, and shall be positioned within + 6.5% (indicated position) of their group average height.

l APPLICABILITY: MODES 1* and 2*,

A_CT ION:

l With a naximum of one APSR inoperable or misaligned from its group i

average htight by more than 4 6.5% (indicated position), operation may I

continue provided that withiii 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

a.

The APSR group is positioned such that the misa11gned rod is restored to within limits for the group average height, or l

f b.

It is determined that the imbalance limits of Specification 3.2.1 are satisfied and movement of the APSR group is pre-vented while the rod remains inoperable or misaligned.

h SURVElLL ANCE REQUIREMENTS

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4.1. 3. 2.1 The position of each APSR rod shall be determined to be within the group average height limit by verifying'the individual rod j

positions at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the psymmetric rod monitor 15 ingperable, then verify the individual rod position (s) of the rod (s), with the inoperable asymmetric rod monitor at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

t 4.1.3.2.2 Unless all APSR are fully withdrawn, the APUt shall be determined to be OPERABLE by moving the APSR rods at least 2% at i

least once every 31 days.

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See Special Test Exceptions 3.10.1 and 3.10.2.

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i DAVIS-BESSE, UNIT 1 3/4 1-21 Amendment No. 162 i

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REACTIVITY CONTROL SYS1[MS POSITION INDICATOR CHANNELS LIMITING CONDITION FOR OPERATION 3.1.3.3 All safety, regulating and axial power shaping control rod absolute position indicator channels and relative position indicator channels shall be OPERABLE and capable of determining the control rob group average positions within i 1.5%.

l ApPLICABillTY: MODES 1 and 2.

ACTION:

a.

With a maximum of one absolute position indicator channel per control rod group or one relative positton indicator channel per control rod group inoperable either:

1.

Reduce THERMAL POWER to < 60% of the THERMAL POWER allow-able for the reactor ecoTant pump combination and reduce the High Flux Trip Setpoint to < 70% of the THERMAL POWER allom ble for the reactor coolant pump combination within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or 2.

Operation may continue provided:

a)

The position of the control rod with the inoperable l

position indicator is verified within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months by actuating its 0%, 25%, 50%, 75% or,100% position l

reference indicator, and b)

The control rod group (s) containing the inoperable position indicator channel is subsequently maintained l

at the 0%, 25%, 50%, 75% or, 100% withdrawn position and verified at this position at least once per 12 i

hours thereafter, and l

c)

Operation is within the lic.its of Specification I

3.1.3.6.

b.

With more than one = relative position indicator channel inoperable. l operation in MODES I and 2 may continue for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months provided all of the absolute position indicator channels are l

OPERABLE.

DAVIS-BESSE, UNIT 1 3/4 1-22 Amendment No.162

REACTivlTY CONTROL SYSTEM $

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ROD DROP TIME

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. LIMITING CONDITION FOR OPERATION I

3.1.3.4 The individual safety and regulating rod drop time from the f

fully withdrawn position shall be < l.58 seconds from power interruption at the control rod drive cabinets to 3/4 insertion with:

s-T,yg >_ 525'F, and

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a.

b.

All reactor coolant puups operating.

APPLICABILITY:

MODES 1 and 2.

ACTION:

With the drop time of any safety or regulating rod determined a.

to exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 and 2.

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b.

With the rod drop times within limits but determined with less f

than 4 reactor coolant pumps operating, operation may proceed provided that THERMAL POWER is restricted to less than or equal to the THERMAL POWER allowable for the reactor coolant pump combination operating at the time of rod drop time measurement.

$_URVEILLANCE REQUIREMENTS 4.1.3.4 The rod drop time of safety and regulating rods shall be demon.

strated through measurement prior to reactor criticality:

2 a.

For all rods following each removal of the reactor vessel f

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head, i

b.

For specifically affected individual rods following any main-tenance on or modification to the control rod drive system which could affect the drop time of those specific rods, and

.c.

At least once every 18 months.

k DAVIS-BESSE, UNIT 1 3/4 1-24 i

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!REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS (Continued)

SURVf!LL AtlCE REQUIREMENTS 4.1. 3. 3 Each absolute and relative position indicator channel shall be determined to be OPERABLE by verifying that the relative position indicator channels and the absolute position indicator channels agree within 3.46% at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the asynrnetric rod monitor is inoperable. then compare the relative position indicator and absolute position indicator channel (s) of the rod (s) with the inoperable asymmetric rod monitor at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , i

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l DAVIS-BESSE, UNIT 1 3/4 1 23 Amendment fio. 162 l

l PJ. ACTIVITY C0ffrROL SYSTEMS BASTS 3/4.1.2 BORATION SYSTEMS (Continued) stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection systen becomes inoperable.

The boron capability required belov 200'T is sufficient to provide a

$87TDOVN KARGIN of it 6k/k af ter menon decay and cooldovn f rom 200'r to 70'F.

This condition requires either 600 gallons of 7875 ppe borated water from the boric acid storage system or 3,000 gallons of 1800 ppa borated vater from the borated vater storage tank.

The bottom 4 inches of the borated water storage tank are not available, and the instrumentation is calibrated to reflect the available volume.

All borte acid tank volume is available. The limits on vater volume, and boron concentration ensure a pH value of between 7.0 and 11.0 of the solution recirculated within containment after a design bails accident.

The pH band minimites the evolution of todine and minimites the effect of chloride and caustic strass cerrosion cracking on sechanical systems and components.

The OPERABILITY of one boron injection systen during KETUELING ensures that this system is available for reactivity control while in NODE 6.

3/4.1.3 MOVABLE CotrTROL ASSEMBLIES The specifications of this section (1) ensure that acceptable power distribution limits are maintained. (2) ensure that the ainlaus SEUTDOVN KAROIN is maintained, and (3) limit the potential effects of a rod ejection accident. OPERABILITT 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.

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original criteria are set. For example, aisalignment of a safety or regulating rod requires a testriction in THERMAL POVER. The react 1vity vortn et a alsa11gned rod is limited for the remainder of the fuel cycle to prevent exceeding the assumptions used in the safety analysis.

The position of a rod declared inop rable due to aisalignment should no't be included in computing the average group position for determining the OFERABILITY of rods with lesser misalignments.

DAVIS-BESSE. UNIT 1 B 3/4 1-3 Amendment No. 123

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RE ACTIVITY CONTROL SYSTEMS,

_ BASES 3/4.1.3.

MOVABLECONTROLASSEMBLIES_(Continuedl The maximum rod drop time pennitted is consistent with the assumed rod drop time used in the safety analyses. Measurement with T

> 525'F and with reactorcoolantpumpsoperatingensuresthatthemeas0EEd~droptimeswillbe representative of insertion times experienced during a reactor trip at operating conditions.

Control rod positions and OPERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with frequent verifications required if an automatic monitoring channel is inoperable, lhese verification frequencies are adequate for assuring that the applicable LCO's are satisfied.

A 1.5% group average position uncertainty is applied to the rod index curves.

Therefore, the position indicators must be capable of supporting this accuracy.

The Surveillance Requirement ensures this accuracy by keeping the RPI calibrated to a "known" position as indicated by the API.

1 Using the API as a "known" position is valid provided two consecutive reed switches are not inoperable.

Having one entire string (i.e., every other reed switch) inoperable is acceptable.

A specific surveillance of the reed switches is not required because:

l 1) When one or more reed switch fails closed, a large API indication of

l asymmetry occurs.

2) Two failed open reed switches in series result in a large indication of asymmetry.

3) Failed open reed switches not in series (up to every other switch) are bounded by the analysis.

Therefore, a reed switch condition not bounded by the analysis will be indicated by API system asymmetry indications.

Technical bpecifiestion 3.1.3.8 provides the ability to prevent excessive power peaking by trcnsient xenon at RATED THERMAL POWER. Operating restric-tions resulting from transient xenon power peeking, including xenon-free startup, are inherently included in the limits of Sections 3.1.3 Rod Insertion Limits), 3.1.3.9 (Axial Power Shaping Rod Insertion Limits), and 3.2.1 (Axial Power imbalance) for transient peaking behavior bounded by the following factors.

For the period of cycle operation where regulating rod groups 6 and 7 are allowed to be inserted at RATED THERMAL POWER, an 8% peaking increase is applied at or above 92% FP.

An 18% increase is applied below 92%

TP.

For operation where only regulating rod group 7 is allowed to be inserted at PATED THERMAL POWER, a 5% peaking increase is applied at or above 92% FP and a 13% increase is applied below 92% FP.

DAVIS-BESSE, UNIT 1 B 3/4 1-4 Amendment No. 4,162

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l REACTIVITY CONTROL SYSTEMS BA$ES l

3/4.1.3 MOVABLE CONTROL ASSEMBLIES (Continued) l L

If these valur% checked every cycle, conservatively bound the peaking effects of all transient xenon, then the need for any hold at a power level cutoff below RATED THERMAL POWER is precluded.

If not, either the power level at which the requirements of Section 3.1.3.8 nust be satisfied or the above-listed e

factors will be suitably adjusted to preserve the LOCA linear heat rate limits.

l The limitation on axial power shaping rod insertion is necessary to ensure that power peaking limits are not exceeded.

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lI DAVIS-BESSE, UNIT 1 B 3/4 1-5 Amendment No. 33. 4. 162 l

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ML20082Q647

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