ML18078A974

Forwards Request for Amend to License DPR-70 & Corresponding Tech Spec Changes.Changes to Safety Tech Specs Involve Deletion of Part Length Control Rods.Affidavit Encl

ML18078A974
Person / Time
Site:	Salem
Issue date:	03/01/1979
From:	Librizzi F Public Service Enterprise Group
To:	Schwencer A Office of Nuclear Reactor Regulation
References
79-07, 79-7, NUDOCS 7903130314
Download: ML18078A974 (16)

Text

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e PS~G Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201 /430-7000 Ref. 79-07 March 1, 1979 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Albert Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors Gentlemen:

REQUEST FOR AMENDMENT FACILITY OPERATING LICENSE DPR-70 UNIT NO. 1 SALEM GENERATING STATION DOCKET NO. 50-272 In accordance with the Atomic Energy Act of 1954, as amended and the regulations thereunder, we hereby transmit copies of our request for amendment and our analysis of the changes to Facility Operating License DPR-70 for Salem Generating Station, Unit No. 1.

This request consists of a proposed change to the Safety Tech-nical Specifications (Appendix A) involving the deletion of the part length control rods. This change has no safety or environmental significance and is, therefore, determined to be a Class II amendment as defined by 10CFR170.22. A check in the amount of $1200 is enclosed.

The removal of the part length control rods is scheduled for the upcoming outage (commencing on March 31, 1979). Therefore, we request that you complete your review of this amendment by March 31, 1979.

This submittal includes three (3) signed originals and .forty (40) copies.

Very truly yours, 790313031'(

Frank rizzi Qeneral Manager -

.Electric Production

• l'K\HSOF SEU\'l('E

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Ref. LCR 79-07 U.S. NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-272 PUBLIC SERVICE ELECTRIC AND GAS COMPANY FACILITY OPERATING LICENSE NO. DPR-70 NO. 1 UNIT SALEM GENERATING STATION Public Service Electric and Gas Company hereby submits proposed changes to Facility Operating License No. DPR-70 for Salem Gen-erating Station, Unit No. 1. This change request relates to Safety Technical Specifications (Appendix A) of the Operating License, and pertains to the deletion of the Part Length Control Rods.

Respectfully submitted, PUBLIC SERVICE ELECTRIC AND GAS COMPANY By*~;J~.,~

FREDERICK W. SCHNEIDER VICE PRESIDENT L_ __

Ref. LCR 79-07 STATE OF NEW JERSEY)

) SS:

COUNTY OF ESSEX )

FREDERICK W. SCHNEIDER, being duly sworn according to law deposes and says:

I am a Vice President of Public Service Electric and Gas Company, and as such, I signed the request for change to FACILITY OPERATING LICENSE NO. DPR-70.

The matters set forth in said change request are true to the best of my knowledge, information, and belief.

Subscribed and sworn to before me thl

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J Notary Puolic of New Jersey My commission expires on )l.f...fJ t. / 9j :3 8/.i.RB/\RA VALLEE f\ NOTARY PUBLIC OF NEW JERSEY My Commission E:{pires nay. .~ 1 :~*:J

PROPOSED CHANGE DELETION OF PART LENGTH CONTROL RODS SALEM UNIT NO. 1 TECHNICAL SPECIFICATIONS Description of Change Removal of the part length control rods from the Salem Unit No. 1 reactor.

Reason for Change Since use of part length rods is prohibited, removal of them pro-vides the following benefits: decreased outage time, decreased radiation exposure and increased maintainability.

Safety Evaluation Removal of the part length control rods does not affect operations, since they are not allowed to be used. Removal of the part length rods does not affect plant basic design nor degrades the system.

There is no increased probability of an accident, no new potential accident, and no previous analyses are affected by removal of the part length control rods. Therefore, this change does not involve an unreviewed safety question.

)

REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.l All full length (shutdown and control) rods,.-e11a all ~ilt le"'~'""' i

~which are inserted in the core, shall be OPERABLE and positioned I within + 12 steps (indicated position) of their bank demand position.

APPLICABILITY: MODES l* and 2*

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, detennine 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 HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. With more than one full i, ~i'* length rod inoperable or misaligned from the bank demand position by more than+ 12 I

steps (indicated position), be in HOT STANDBY within 6-hours.

c. With one full .e, ~aPt length rod inoperable due to causes other than addressed by ACTION a, above, or misaligned from f

its group step counter demand height by more than + 12 steps (indicated position), POWER OPERATION may continue-provided that within one hour either:

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

2. The 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 analysis of the potential ejected rod worth is performed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and the rod worth is determined to be < 0. 95~~ t:.k at zero power and < 0.21% t:.k at RATED THERMAL POWER for the remaTnder of the fuel cycle, and

• See Special Test Exceptions 3.10.2 and 3.10.3.

SALEM - UNIT 1 3/4 1-18 l_

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REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS

~IMITING CONDITION FOR OPERATION 4A' 3.1.3.2 All shutdown,~control &~i paPt .1e"!t~ eeRtte1 rod position indi-

~ator channels and the demand position indication system shall be OPERABLE f

and capable of determining the control rod positions within + 12 steps.

APPLICABILITY: MODES l and 2.

ACTION:

a. With a maximum of one rod position indicator channel per group inoperable either:

1. Determine the position of the non-indicating rod(s) in-directly by the movable incore detectors at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and i1T1T1ediately after any motion of the non-indicating rod which exceeds 24 steps in one direction since the last determination of the rod 1 s position, or

2. Reduce THERMAL PO~ER TO < 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 a maximum of one demand position indicator per bank inoperable either:

1. Verify that all 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 12 steps of each other at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or

2. Reduce THERMAL POWER to < 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 />.

SURVEILLANCE REQUIREMENTS 4.1.3.2 Each rod position indicator channel shall be determined to be OPERABLE by verifying the demand position indication system and the rod position indicator channels agree within 12 steps 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 indicator channels at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SALEM - UNIT 1 3/4 1-20

REACTIVITY CONTROL SYSTEMS PART LENGTH ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION All part length rods shall be fully withdrawn.

ACTION:

ILlTY: MODES 1* and 2*

With a maxim of one part length rod not fully withd hour either:

a. Fully w hdraw the rod, or b.

SURVEILLANCE RE UIREMENTS 4.1.3.6 Each part length r etennined to be fully withdrawn by:

a. Verifying the osition of the pa length rod prior to increasing T RMAL POWER above 5% RATED THERMAL POWER, and

b. Verifyin , at least once per 31 days, at electric power has been

• connected from its drive mechani of reaker from the circuit.

Test Exceptions 3.10.2 and 3.10.3 SALEM - UNIT 1 3/4 1-26

POWER UISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) b) At least once per 31 EFPD, whichever occurs first.

2. When the Fx; is less than or equal to the F:~P limit for the appropriate measured core plane, additional power distribution maps shall be taken and Fx; compared to F~~P and Fx; at least once per 31 EFPD.

e. The Fxy limits for RATED THERMAL POWER within specific core planes shall be:

1. F:~P !. 1.71 for all core planes containing -eitlit!'1& bank 2.

"D" control rods ;p iRf ~aFt leA!~~ Pe~i; and F~;P !. 1.55 for all unrodded core planes.

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f. The Fxy limits of e, above, are not applicable in the fol-lowing core plane regions as measured in percent of core height from the bottom of the fuel:

1. Lower core region from 0 to 15%, inclusive.

2. Upper core region from 85 to 100% inclusive.

3. Grid plane regions at 17.8 + 2%, 32.1 + 2%, 46.4 + 2%,

60.6 + 2% and 74.9 + 2%, inclusive. - -

4. Core plane regions within + 2% of core height (+ 2.~8 inches) about the bank demand position at the bank 0 or 11 11 part length control rods.

g. Evaluating the effects of Fxy on Fg(Z) to detennine if Fg(Z) is within its limit whenever Fx; exceeds Fx;.

4.2.2.3 When Fg(Z) is measured pursuant to specification 4.10.2.2, an overall measured Fg(Z) shall be obtained from a power distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.

SALEM - UNIT 1 3/4 2-7 Pmendment No. 9

l *** , POWER

.. DISTRIBUT. LIMITS QUADRANT POWER TILT RATIO

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LIMITING CONDITION FOR OPERATION 3.2.4 THE QUADRANT POWER TILT RATIO sha11 not exceed 1.02.

APPLICABILITY: MODE 1 ABOVE soi OF RATED THERMAL POWER*

ACTION:

a. With the QUADRANT POWER TILT RATIO detennined to exceed 1.02 but < 1 .09:

l. Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

a) Either reduce the QUADRANT POWER TILT RATIO to within its limit, or

• b) Reduce THERMAL POWER at least 3i from RATED THERMAL

~OWER for each 1% of indicated QUADRANT POWER TILT RATIO in excess of 1.0 and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

2. Verify that the QUADRANT POWER TILT RATIO is within its limit within l4 hours after exceeding the limit or reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within the next l hours and reduce the Power Range

• Neutron Flux-High Trip setpoints to < 55% of RATED THERMAL POWER wi thi 11 the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

3. Identify and correct the cause of the out of limit con-dition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL power may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified acceptable at 95% or greater RATED THERMAL POWER.

b. With the QUADRANT POWER TILT RATIO detennined to exceed 1.09 due to misalignment of either a shutdownA'Control .eia ~1"!

1eFI§~ rod:

1. Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for each li of indicated QUADRANT POWER TILT RATIO in excess of 1.0, within 30 minutes.

2. Verify that the QUADRANT POWER TILT RATIO is within its

( limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after exceeding the limit or

• See Special Test Exception 3.10.2.

SALEM - UNIT 1 3/4 2-11 Amendment Uo. 9

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POWER DISTRIBUTION LIMITING CONDITION FOR OPERATION (Continued) reduce THEP.HAL POWER to less than 50% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High trip Setpoints to < 55% cf RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

3. Identify and correct the cause of the out of limit con-dition* prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour fer 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified acceptable at 95% or greater RATED THERMAL POWER.

c. With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due to causes other than the misalignment of either a shut-* I down:.{control .e1 pet t ~eA!i~ rod:

l. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High Trip Setpoints to < 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. -

2. Identify and correct the cause of the out of limit con-dition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified at 95% or greater RATED THERMAL POWER.

SURVEILLANCE REQUIREMENTS 4.2.4 The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 50% of RATED THERMAL POWER by:

a. Calculating the ratio at least once per 7 days when the alarm is OPERABLE.

b. Calculating the ratio at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during steady state operation when the alann is inoperable.

c. Using the movable incore detectors to determine the QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when one Power Range Channel is inoperable and THERMAL POWER is > 75 percent of RATED THERMAL POWER.

SALEM - UNIT 1 3/4 2-12

3/4.10 SPECIAL TEST EXCEPTIONS SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of control rod worth and shutdown margin provided:

Reactivity equivalent to at least the highest estimated control I rod worth is available for trip insertion from OPERABLE control n>d(s), ....

". A\1 .P~t r.,.ngth'(Ods ~ wittttrawn ~~as~h~~t~

po)4tio\ an~PE~LE.

APPLICABILITY: MOOE 2.

ACTION:

a. With any full length control rod not fully inserted and with less than the above reactivity equivalent available for trip insertion er the part length rods not within their withdrawal limits, inmediately initiate and continue boration at> 10 gpm of 20,100 ppm boric acid solution or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

I' .

With all full length control rods inserted and the reactor sub-b.

critical by less than the above reactivity equivalent, irrmediately

• initiate and continue boration at> 10 gpm of 20,100 ppm boric acid solution or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE REQUIREMENTS 4.10.1.1 The position of each full length and part length rod either partially or fully withdrawn shall be detennined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

4.10.l.2 Each full length rod not fully inserted shall be demonstrated capable of full insertion when tripped from at least the soi withdrawn position within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1 *

\ . ~3 p t ~par~engt le th r !_ 10 rods eps ~11 "thin~em~trat~PE~LE hou prio to r ucing b~ing e

DOW MARG SALEM-UNIT l to 1 s than he 1 its 3/4 10-1 Spe 'ficat n 3. 1.1.

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SPECIAL TEST EXCEPTIONS GROUP HEIGHT, INSERTION ANO POWER DISTRIBIJTION LIMITS LIMITING CONDITION FOR OPERATION 3.10.2 The group height, insertion and power distribution limits of Spec.ifications 3.1.3.1. 3.1.3.4. 3.l.3.5, a.l.3.6, 3.2.1, and 3.2.4 may I be suspended during the perfonnance of PHYSICS TESTS provided:

a. The THERMAL POWER is maintained < ssi1 of RATED THERMAL POWER, and -

b. The limits of Specifications 3.2.2 and 3.2~3 are maintained and determined at the frequencies specified in Specification

~.10.2.2 below.

APPLICABILITY: -MODE 1 ACTION:

With any of ~he limits of Specifications 3.i.2 or 3.2.3 being exceeded

1. hile the requirements of Specifications 3.1.3.1, 3.1.3.4, 3.1.3.5, 3.l.3.6, 3.2.l and 3.2.4 are suspended, either:

a *. Reduce THERMAL POWER sufficient to satisfy the ACTION require-ments of Specifications 3.2.2 and 3.2.3, or

b. Be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.10.2.l The THERMAL POWER shall be detennined to be< as:* of RATED THERMAL POWER at least once per hour during PHYSICS TE'S"'TS. .

4.10.2.2 The Surveillance Requirements of Specifications 4.2.2 and 4.2.3 shall be performed at the following frequencies during PHYSICS TESTS:

a. Specification 4.2.2 - At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b. Specification 4.2.3 - At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• see page 3/4 10-2a.

SALEM-UNIT 1 3/4 10-2 Amendment No. J, (,

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L. SPECIAL TEST EXCEPTIONS PHYSICS TESTS LIMITING CONDITION FOR OPERATION 3.10.3 The limitations of Specifications 3.1.l.4, 3.1.3.l, 3.1.3.4, ._,.,./. J 3.1.3.5,*~i e.1.3.e may be suspended during the performance of PHYSICS TESTS provided:

a. The THERMAL POWER does not exceed 5% of RATED THERMAL POWER, and

b. The reactor trip setpoints on the OPERABLE Intermediate and Power Range Nuclear Channels are set at < 25% of RATED THERMAL POWER. -

APPLICABILITY: MODE *2.

ACTION:

With the THERMAL POWER > 5% of RATED THERMAL POWER, irrmediately open the reactor trip breakers.

SURVEILLANCE REQUIREMENTS 4.10.3.l The THERMAL POWER shall be detennined to be< 5~~ of RATED.

THERMAL POWER at least once per hour during PHYSICS TESTS.

4. 10.3.2 Each Intermediate and Power Range Channel shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating PHYSICS TESTS.

SALEM-UNIT l 3/4 10-3

• * )

REACTIVITY CONTROL SYSTEMS BASES 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inoperable. These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.

e r tric *o~pr. hib i~g a~t ni/Sgh od;w*er~io e~nu s!Zh*

adv se p er s pes d r pid cal ewer

• ange whic may feet ON con dera ans no occu as

• resu of p t le th r ins tion ring pera on.

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SALEM - UNIT l B 3/4 1-4

POWER DISTRIBUTION LIMITS BASES 3/4.2.2 and 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHArlNEL FACTORS-N Fq(Z) and FLIH The limits on heat flux and nuclear enthalpy hot channel factors ensure that 1) the design limits on peak local po.,.1er density and minimum

• DNBR are not exceeded and 2) in the event of a LOCA the peak fuel clad temperature will not exceed the 2200°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 hot channel factor limits are maintained provided:

a. Control rod in a single group move together with no individual rod insertion differing by more than + 12 steps from the group demand position. -

b. Control rod groups are sequenced with overlapping groups as described in Specification 3. 1.3.5.

(

c. The control rod insertion limits of Specification* 3.1.3.5

• Rd 1,1,3.~ are maintained. I

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

The relaxation in FNH as a function of THERMAL POWER allows change~

in the radial power shap~ for all permissible rod insertion limits.

F~H will be m~int~ined within its limits provided conditions a thru d aoove, are maintained.

When an F measurement is taken, both experimental error and man-ufacturing tolQrance must be allowed for. 5% is the appropriate allowance for a full core map taken with the incore detector flux mapping system and 3~ is the appropriate allowance for manufacturing tolerance.

When FN is measured, experimental error must be allowed for and 4%

is the apprA~riate allowance for a full coreNmap taken with the incore detection system. The specified limit for F H also contains an 83 allow-ance for uncertainties which mean that normat operation will result in F.H ~ 1.55/1.08. The 8% allowance is based on the following considera-t'fbns: *

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SALEM - UNIT 1 B 3/4 2-4

., l: * '

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DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be main-tained for a maximum internal pressure of 47 psig and an air temperature of 271°F.

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.l The reactor core shall contain 193 fuel assemblies with each f~el assembly containing 264 fuel rods clad with Zircaloy -4. Each fuel rod shall have a nominal active fuel length of 143.7 inches and contain a nominal total weight of 1743 grams uranium. The initial core loading shall have a maximum enrichment of 3.35 weight percent U-235.

Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 3.5 weight percent U-235.

CONTROL ROD ASSEMBLIES (

5.3.2 The reactor core shall contain 53 full length aRel g ~art len9th control rod assemblies. The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The ~art leA§t~

conbol rod assemblies shall eeRtaiA a ReffiiAal 36 inc~es ef absorber material at tAeir lewer @Reis. The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium.

All control rods shall be clad with stainless steel tubing. -The balance of the 'teief leA§th iA the ~art leA§tA peas st:iall contain a1tiff! i n1:n11 e>E i ele ,

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.l The reactor coolant system is designed and shall be maintained:

SALEM - UN IT l 5-4