ML19210B155

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Tech Spec Change Request 4 Supporting Licensee Request to Change DPR-50,App a to Impose Different Operating Limits as Derived from Sections of B&W Topical ECCS Analysis & Thereby Comply w/10CFR50.46
ML19210B155
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 09/05/1974
From: Arnold R
METROPOLITAN EDISON CO.
To:
Shared Package
ML19210B153 List:
References
NUDOCS 7911040086
Download: ML19210B155 (14)
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.4 ,0- no e-Thic Technical Specifica; ion Change Request is submitted in suppor; cf Me ropoliten Edison Cor.pany's requcc for Ce cission authority to change Append'x A to Operating License I:0. DPR-30 for the Three Mile IslanJ Ilueleer Genercting Station, Unit 1. This change would incorporate Technical Specification Chen;e Request No. k in order _t; bring the Three Mile I: lend Unit 1 reactor int:

conformance with the requirements set forth in the Stcff " Determination of Request for e:: ten:-icn of time for submittel of Evaluenions Required by Accep tnce Criteric for E~ergency Core Coolin;; Systems", cated August 5, 1974.

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Three Mile Island Nuclear Generating Station, Unit 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Chance Reauest No. k Applicant hereby requests the Commission to change Appendix A as shown by the enclosed changed pages designated "TMI-l Change Request No. h."

Reason for Chance Recuest Changes are requested to impose different operating limits as derived from sections of the B&W Topical ECCS analysis and thereby ensure compliance with 10CFR50.h6.

Safety Analysis Justifyine Chance Change Request No. L establishes operating limits that are in accordance with the results contained in the B&W Topical report, BAW-10091, B&W's ECCS Evaluation Model Report With Specific Application to 177 FA Class Plants With Lovered Loop Arrangement. The safety evaluation supporting these limits is included in B&W Topical Report Nos. BAW-10091 through 10095

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3 3.5 2 C0: 20L E03 OEDUP 2:D FO'.ZR DISTRI30TIO:: LI:'IIS Arrlicability This specification applies to power distributien and cperati:n of control rods during power operation.

Objective To assure an acceptable core power distribution during power Operation, te cet a limit on potential reactivity insertion frc a hypothetical control rod ejection, and to assure core suberiticality after a reactor trip.

Snecification 3.5.2.1 The available shutdeve cargin shall not be less than one per-cent L::/k with the hishest worth centrol rod fully withdrawn.

3.5.2.2 Operation with inoperable rods:

a. Operatien with more than one inoperable rod as defined in Specification h.7.1 and L.7.2.3 in the safety or regulating rod banks shall not be pe.vitted.
b. If a control rod in the regulating and/or safety rod ban':s is declared inoperable in the withdrawn positien as defined in Specification Paragraph h.7.1.1 and k.7.1.3, an evaluation shall be initiated i=nediately to verify the existence cf one percent Ak/k hot shutdown margin. 3 oration cay be initiated to increase the available rod worth either to ec pensate for the vorth of the inoperable rod or until the regulating banks are fully with-Fravn, whichever occurs first. Sicultaneously a program of exercising the re=aining regulating and safety rods shall be initiated to verify operability.
c. If within one hour of determination of an inoperable red as defined in Specification h.71, it is not deterrined that a one percent Ak/h hot shutdown =argin exists conbining the vorth of the inoperable rod with each of the other rc:is, the ree: tor shall be brought te the hot standby condition until this nirgin is established.
d. Fellowing the determination of an inoperable rod as defined in Specification h.71, all rods shall be exercised within 2h hors and exercised weekly until the r0d prcblen is solved.
e. If a control rod in the regulating or safety rod groups is declared inoperable per L.7.1.2, p;ver shall be reduced to 60% of the themal power allevable for the reactor coolant purp conbination.

1587 006 3-33

-I Change Request No. L C

f. If a control red in the regulating or ehial power shaping (

g oups is decle. red inoperable per Specification L.7.1.2. ,

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operation may continue provided the rods ir the group are positiened such that the rod that was declared incperable is maintained within allowable group average positien limits of Specification k.71.2.

g. If the inoperable rod in Paragraph "E" above is in grcups 5, 6, 7, or 8, the other rods in the group shall be tri=ned to the sa=e position. Normal operation of 100 percant of the ther=al power allowable for the reactor coolant pump cct-bination may then continue provided that the rod that was declared inoperable is maintained within allowable grcup average position linits in 3 5 2 5 3.5.2 3 Tne vorth of a single inserted control rod shall not exceed 0.65 percent Ak/k at rated power or 1.0 percent ak/k at hot zero power except for physics testing when the req irenent of Specification 3.1 9 shall apply.

3.5.2.L Quad-ant tilt:

a. Except for physics tests if quadrant tilt exceeds 4 percent, power shall be reduced immediately to below the power level cutoff (see Figures 3.5-2A, 3.5-23, and 3 5-20). Moreover the l power level cutoff value shall be reduced 2 percent for each 1 percent tilt in excess of 4 percent tilt. For '

less than four pump operation, thermal power shall be reduced 2 percent of the thernal power allowable for the reactor coolant pump combination for each 1 percent tilt in excess of 4 percent.

b. Within a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, the quadrant pcwer tilt shall be reduced to less than 4 percent except for physics tests, or the following adjustments in setpoints and licits shall be made:
1. The protection system reactor power / imbalance envelope trip setpoints shall be reduced 2 percent in power for each 1 percent tilt.
2. ~he control rod group withdrawal limits (Figures 3.5-2A t

3.5-23, 3 5-2c, end 3 5-2D) shall be reduced 2 percent in power l for each 1 percent tilt in excess of 4 percent.

3. The operational imbalance limits (Figure 3.5-2E) shall be reduced 2 percent in power for each 1 percent tilt l in excess of 4 percent.

1587 007 3-3h

-I Change Request No. L

c. If quabant tilt is in excess of 25 percent, except for physics tests or diagr.cstic testing, the reactor vill be placed in the het shutdcyn condition. Diagnos tic testing during pcVer cperation with a quadrant power tilt is pe_ itted provided the thernal pcVer allevable fer the reacter ccciant pump cc binations is restricted as stated in 3.5.2.L.a, above.
d. 0;aadrar.t tilt shall be monitored on a minimum frequency of cnce ever/ two hours during power operation above 15 percent of rated pover.

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-I Change Request No. h 3525 Centrol roi positions:

a. Operating rod group overlep s'icll not exceed 25 percent, 25 percent, between two sequential groups except for physics tests.

1 Except for physics tests or exercising con. trol rods, the control rod insertion / withdraw =' 'i-its are specified on Figures 3 5-2A (for up to 100 full pcwer days of opera-tion), Figure 3 5-23 (for 100 to 4L2 full power days of operation), Figure 3 5-2C (for after hh3 full power days of operation) for four pump operation, and Figure 3 5-29 for three or two pump operation. If the control rod position limits are exceeded, corrective reasures shall be taken 4--adiately to achieve an acceptable control rod position.

Acceptable control rod positions shall be attained within four hours.

c. Except for physics tests, power shall not be increased above the power level cutoff (See Figures 3.5-2A, 3 5-23, and 3 5-20) unless the xenon reactivity is within 10 percent of the equilibrium value for operation at rated power and asy=ptotically approaching stability.
d. Core idbalance shell be monitored on a =inimum frequency

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of once ever# two hours during power operation above 40 r

percent of rated power. Corrective cessures (reduction of Dibalance by AFS2 novement and/or reiuction in reactor power) shall be ta%en to maintain operatien within the envelope defined by Figure 3 5-2E. If the imbalsnce is not within the envelope defined by Figure 3 5-22, corrective meacures shall be taken to achieve an acceptable imbalance. If en acceptable imbalance is not achieved within four hours, reactor power shall be reduced until idbslance limits ere met,

e. Safety roi limits are given in 3 1 3.5 3 5.2.6 The control rod drive patch panels shell be locked at all thnes with Ihrited cecess to be authoriced by the superintend?nt.

3 5.2.7 A power cap shall be taken to verify the expected power distri-bution at periodic intervals of approximately 10 full power days using the incore instrumentet*cn detection system.

Bases The power-imbalance envelope defined in Figure 3 5-2E, is based on LOCA analyses which have defined the mexitun linear heat rate (see Figure 3 5-2F) such that the maximum clad temperature 4111 not exceed the Final Acceptance Criteria.

Operation outside of the power imbalance envelope alone does not constitute a situation that would cause the Final Acceptance Critaria to be exceeded should a l LOCA occur. The power inbalance envelope represents the boundary of operation 3-35 ra7 jus pJgg

.. -I Change Request No. k limited by the Final Acceptance Criteria only if the cen'.rol rods are at the withdrawal / insertion lirits as defined by Figures 3 5 2A, 3. 5 23, 3 5-2C, s..l 3 5-2D and if a I + percent quadrant pcver tilt exists . Additional consertatist is intro-ducted by application of:

a. Nuclear uncertainty factors
b. Tne:=21 calibration uncertainty
c. Fuel densification effects
d. Hot rod ranufacturing tolerance factors En] niO sG, V1U 3-35a

T"'-I Change Pequest No. k The 30 percent overlap be. .1 successive control rod grou.3 .s allcwed since the worth of a rod is lover at the upper and lover part of the strche. Control rods are arranged in groups or banks defined as follows :

Grono Functier [

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D ** "" "D l Safety D JP D

,d.d }[ f 2 Safety _oo n 3 Safety h Safety 5 Re gulating 6 Re gulating 7 Xenon translent override 8 APSR (axial power shaping bank)

Control rod groups are withdrawn in sequence beginning with group 1. Groups 5, 6 and 7 are overlapped 25 percent. The nor=al position at pcVer is for g-oups 6 and 7 to be partially inserted.

The mininu= available rod vorth provides for achieving hot shutdown by reactor trip at any time asst =ing, the highest vorth control rod retains in the full out position (l).

Inserted rod grcups during power operation vill not contain single rod worths greater than 0.65 percant ak/k . This value has been shown to be safe by the safety analysis of the hypothetical rod ejection accidentt2). Single inserted control rod worth of 1.0 percen Ak/k at beginning of life , hot, zero power would result in the same transient peak thermal power, and therefore, the sane environmental consequences as a 0.65 percent Ak/k ejected rod vorth at rated power.

The plant computer vill scer. for tilt and imbalance and will satisfy the tech-nical specification requirements. If the co. puter is cut of service, then nanual calculation for tilt above 15 percent power and i balance above k0 percent power cust be performed at least ever" two hours until the conputer is returned to service.

The quadrant power tilt limits set forth in Specification 3.5.2.h have been established within the ther=al analysis design base using the definition of quadrant power tilt given in Technical Specifications, Section 1.6.

During the physics testing progren, the high flux trip setpcints are adminis-tratively set as follows to assure an additional safety cargin is provided:

Test Pcver Trip Se n ci..t 0 <5%

15 505 40 50%

50 60%

75 85%

>75 105.55 REFERENCES (1) FSAR, Section 3 2.2.1.2 (2) FSAR, Section lk.2.2.2 o: .

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