ML20126C847

Amend 29 to License DPR-54,terminating ECCS Exemption to 10CFR50.46 for Fuel Loading Used During Cycle 4

ML20126C847
Person / Time
Site:	Rancho Seco
Issue date:	03/31/1980
From:	Reid R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20126C846	List: ML20126C843 ML20126C847 ML20126C851 ML20126C856
References
NUDOCS 8004100246
Download: ML20126C847 (27)

Text

.

g,R R ECyS e

UNITED STATES O

{y " )

NUCLEAR REGULATORYCOMMISSION

.j WASHINoTON, D. c. 20sss o

t

\\.'.v.../

SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Anendment No. 29 License No. DPR-54 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Sacramento Municipal Utility District (the licensee) dated October 3,1979, as supplemented February 19, 1980 and February 27, 1980, 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

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

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

i b

{

8004100

. 2.

Accordingly, the license is 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. DPR-54 is hereby amended to read as follows:

i (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 29, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

I' FOR THE NUCLEAR REGULAT RY COMMISSION ls

f, dis

.obert W. Reid, Chief

~

Operating. Reactors Branch #4 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance: March 31, 1980 l

ATTACHMENT T0' LICENSE A"ENDMENT NO, 29 FACILITY OPERATING LICENSE NO. DfR-54 DOCKET NO. 50-312 Revise Appendix A as follows:

Remove Pages Insert Pages viii & ix viii.8 ix Fi gure 2.1-2 Figure 2.1-2 1

1 Fi gure 2. 3-2 Figure 2.3-2 3-17 & 3-18 3-17 & 3-18 Fi gures 3.5.2 3.5.2-11 Fi gures 3.5.2 3.5.2-11 3 3-46 3 3-45 5 5-5 5 5 -5 Chances on the revised pages are shown by narginal lines.

Pages 3-4 3 and 5-3 are ;n-hinged and are provided for your convenience only.

l t

s PANCHO SEL1 UNIT 1 TECHNICAL SPEC 1.~ICATIONS i

l LIST OF FIGUP.ES l

Firure 2.1-1 Core ? o:ee:1e Safe:y Li 1:. Pressure vs. Te=pera:ure 2.1-2 Core Prete::ie Saf e:y Li=1:s, Reacto ? cue

!= balance 2.1-3 Core Protective Saf ery Bases 2.3-1

.? ote::ive Sys:e=.W.ari=u= Allevable Se: points, ? essure,vs.

Te=p era:u:e

2. 5-2

? c:e::ive Sys:el: Ma.xi=u= Allevable Se:poin:s, Reactor Power

!=b a.las e e 3.1. 2-1 Keae::: C: clan: Sys:e= ?; essure-Te=: era:ure L1=1:s f er Hea:up

.e..

r. e.. s..

c, m.v.

3.1.2-2

?.ez ::: 00:.a : Syste= ?: essure-Te=: era:ure L1=1:s fer Cecideve

,........,e m. v.

.s....

3.1. ~- 3

servi:e ' ed. a=d Hydres:a:i: es: (5 I??Y) Hea up and Cool-devn 3.1.i-1

# :itg ? essure vs. Te=perature fer C ::rel Rod Drive 0; era:10:

3.5.2-1 bd ~::ex vs. ? cue: Level f : 7 ur-?=p Opera:1et; O :o 160 M. *.*

2.3.2-1 b d ::de: es. ?:ve: Level f e; 7:ur-?u=p Opera:1er., 140 e 10 l

.=. D s

i

2. 5. :- 3 bd Ind e= vs. ? cue: Level f=

? cur-?. p Opera:ies.

290:e 345 I

m..D 3.3.2-4 bd I:de.= vs. Pe0er Level for ~hree-?u=p opera:1e=, O to 160

m..m

3. ~

bd ::de= vs. Power Level for :ree-?u=: Opera:i n,140 :: 310

m.,

• 3.*-6 Md

-der. v:. ?:ve: Level f:: hree-?u=p opera-ica, 290 :: 3',5 l

m..,.

2. 3. - 7

.057 Wi:hd:av C vs. ? cue. eve;, O :: 150 7 ?

2.5. -!

A?!? 21:hdraval vs. ?:v er *. eve.;.

"'O :: 310 I27 0 l

. 8, 2.1 29

.111

..-e

=en:

4 L ST OT TICt.7.I5 (Cen:' d)

Tirures 3.5.2-9 Cere I= balance vs. Fever Level, O :e 160 ET?D 3.5.2-10.-

Core I= balance vs. Power Level,110 :o 310' E7?D l

3.5.2-11 Cere I: balance vs. ?cver Level. 290 to 345 NF?D 3.5.2-12 LOCA Li=1:ed F.ax1=.== Allevable L1: ear Hea: Ra:e 3.5.4-1 Incere Ins: u=entation specification Axial I: balance I=dicatics

3. 5. 4-2 1:cere Ins: rte.enta:1es specifica:1en Radial 71cx Til: Indication 3.5.4-3 1:cere I:s:n=enta:1e: specifica:Len 4.13-1 Main Steam Inser-ice Inspection 4 12-2 Main Teedvater I:se:Tice Inspection l

4.13-3 Main Stea: Du=p Inservice Inspection 6.2a1 SMITD Organiza:ie: Chart 6.2-2 Plan: Organizatie: Char;

.cend:en: No. E,. X 29 ix

Figtre 2.1-2 Core l'rotection Saf ety Licits, Reactor Po'er 1= balance THERWAL P0rER LEVEL, 5 120

( -3'6. 9.112 )

CURVE 1

(+35.8.112)

-110 ACCEPTABLE 4 PUMP

-100 OPERATION

(+59.5,96.5)

( -4 7.1. 9 0. 5 )

- 90

( 36.9,84.6)

CURVE 2 (35.8,84,6)

- 80 ACCEPTABLE 4 & 3 PUMP

,70 OPERATION

(+ 59. 5. 69.1 )

(-4.1.63.7)

( 36.9.57.4) 60 cupyr 3 (35.B,57.4)

ACCEPTABLE

- 50 4, 3 & 2 PUMP

- 40

~ )

' 47,i,3 5.5)

- 30

- 20

- 10

-50

-40 20 0

20 40 60 Reactor power it.:a lance, 5 URiE RE10 TOR COOLANT OESIGN FL0f. GPP 1

357,500 2

2EE,374 3

157.9E6

~

A c. ire:: :::. 4"', 2 9

Fieure 2. 3-2 Procective System Maximum Allowable Setpoints, Reactor Power 1: balance THERMAL POWER LEVEL, f; I

l

( 26,105) CURVE 1 j

110 (26,105) 4*

1. .g@

@ l ACCEPTABLE 100

,F 4 PUMP OPERATION l

(49,90) e I

- 90

(-36,84)

CURVE 2 I

I (-25,78.1 )

80 1 (26,78.1)

I l ACCEPTABLE l 4 & 3 PUMP

- 70 l

I (49,63.1 )

l OPERATION

- 60 I

( 36,57.1) f626,50.9)

CURVE 3 l(2B,50.9) 50 ACCEPTABLE I

4, 3 f. 2 40

~

l PUMP l

(49,35.9) l OPERATION

( -3 6,2 9. 9 )

I 30 I

I y

• g

- 20

,l a!

10 n

n

ll

~

-=

l

-60

-40 20 0

20 40 60 Reector Pcwer imbalance, f; CURVE REACTOR COOLANT DESIGN FLOW, GPM 1

357,600 2

288,374 3

187,986 l

1

.. e n d:sen: :::. K 29

RANCHO SECO' UNIT 1 TECERICAL SPECIFICATIONS L1=iting Conditions for Operation 3.2 BIGH FPISSURE INJECTION AND CECAL ADDITION SYSTEMS Aeplicability Applies to 'the operational status of high pressure injection and chemical ad-dition systems.

Obj ective To provide for adequate boration under all operating conditions to ensure ability to bring the reactor to a cold shutdown condition.

I Specification The reactor shall not re=ain critical unless the following conditions are cec:

3.2.1 Two pu=ps capable of supplying high. pressure injection are operable j

(also see Specification 3.3.2).

l 3.2.2 The borated water storage tank and its flow path to the reactor for high pressure injection are operable.

3.2.3 A source of concentra:ed boric acid solution in addition to the borated water storage tank is available and operable.

This requirement is ful-filled by the concentrated boric acid storage tank.

This tank shall contain at least the equivalent of 10,000 gallons of 7,100 pp: boren.

Syste piping and valves necessary to establish a flow path for high pressure injection shall also be operable and shall have at least the.

same te=perature a's the boric acid storage tank.

One associated boric acid pu=p is operable.

The concentrated boric acid storage tank va:er I

shall not be less than 707, and at least one channel of hea: tracing shall be operable for this tank's associated piping.

The conce ::a:ed boric acid storage tank boron concentration shall not exceed 8,500 pp b o ron.

Bases The makeup and purification syste= and che=ical addition syste=s provide cen-trol of the reactor coolant syste= boron concentration.1 This is normally ae-ce=plished by using either the makeup pu=7 or one of the two high pressure injection pu=ps in series with a boric acid pu=? associated with the concen-trated boric acid storage tank.

The alternate method of boration will be the use of the makeup or high pressure injection pu=ps taking suction directly-fro the borated water storage tank.*

The cuantity of boric acid in storage frc= either of the two above-mentioned sources is sufficient to bora:e the reactor coolant syster to a 1 percent sub-critical =argin in the cold condition (70F) at the wors time in core lif e with a s:uch control rod asse bly.

The =ari=u: required is the equivalent of c105 l

gallons of 7100 pp: boron.

This recuire=ent is satisfied by requiring a =in-

~*$"

e of 10,000 gallons of 7100 pp in the concentrated boric acid d-"-

-17 t

Arendeen: Sc.29

RANCHO SECO UNIT 1 TECimICAL SPECIFICATIONS storage tank during critical operations.

The =ini=un volume for the borated water storage tank (390,000 gallons of 1800 ppm boren), as specified in sec-tion 3.3, is based on refueling volu=e requirements and easily satisfies the cold shutdown require =ent.

The specification assures that the two supplies are available whenever the reactor is criti:a1 so that a single failure will not prevent boration to a cold. condition.

The =ini=um volu=es of boric acid solution given include the boren necessary to account for xenon decay.

The quicisest cathod allows for the necessary boren addition in less than one hour.

The primary method of adding boron to the primary system is to pu=p the concentrated boric acid solution (7100 ppm boron, minimum) into the makeup tank using the 50 gpm boric acid pe=ps.

Using only one of the rwo boric acid pu=ps, the required volu=e of boric acid can be injected in less than 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

The

{

alternate method of addition is to inject boric acid from the borated water storage tank using the high pressure injection pumps.

Concentration of boron in the concentrated boric acid storage tank =sy be higher than the concentration which would crystallize at ambient conditions.

For this reason and to ensure that a flew of boric acid is available when needed', this tank and its associated piping will be kept above 70F (30F above the crystallization te=perature for the concentration present).

Once in the high pressure inj ection systes, the cencentrate is 'sufficiently well =1xed and dilutef so that nor=al syste= tengera:ures ensure beric acid solubility.

Tse value of 707 is significantly above the etystallization te=perature for a so-lution containing 12,200 ppe boren.

RETIRINCIS 1 FSAE subsections 9.2 and 9.3.

2 FSA?. Figure 6. 2-1.

Te '--'-*' cpecification 3.3.

5 Aren::en: 5:. 29 3-15

Figure 3.5.2-1 Rod Index Vs Power Level for Four-Pu=p Operation, O to 160 EFPD 110 105 135,102)

(280,102) 100 95 OPERATION NOT (280,92) 90 33 ALLORED 80 75 (255,80) 70 SHtJTDOWN OPERATION E5 LIMIT RESTRICTED 50 f 55

)

50 (51,50)

(232,50) 45 40' 35 30 25 OPERATION l

20 PERMISSIBLE 15 (E.15) 10

'(0,10)

~

0,0)

(

t 0

20 40 60 EC 100 120 140 150 150 200 220 240 250 250 300 Roc incex i

0 25 50 75 100 0

25 50

75 100 Band 7 Bant 5 0

25 50 75 100 Sank 6 i

j..3.d e.: '::. E, 29

Fig ur e 3.5.2 -2 Rod Index Vs Power Level for Four-Pu:np Operation, 140 to 310 EF?D 110 105 (187.102)

)

100 55 OPERATION HOT (280.92)

ALLOWED 50

-c (265,80)

C*

20 75 DPERATION sHvTocwN 7g LIMIT RESTRICTE0 F5 EO f 55 c_

(109,50)

E

=0 (232,50) 15

- V n'

"O OPERATION

~5 PERMISSIBLE 20 (15.15) 10 sC.10)

( 0. 0,)

20 40 50 50 100 120 140 150 150 200 220 240 260 280 300 Rea incex i

i i

3 25 50 75 100 0

25 50 75 100 Bank 5 Bank 7 0

25 50 75 100 Bank 6 f.:c:d:s.: '::. 7, 29

Figure 3.5.2-3 Rod Index Vs Power Level for Four-Pump Operation, 290 to 345 EFFD 11C 105 (195.102)

(275,102) 1C0 II

~

OPERAT10N (259,92) e0 HOT ALLCIED OPERATl0N

~

E"

~

SHUTDOWN RESTRICTED (236.80)

SD Ligg7 75 70 e:

~'

g OPERATION c,

PERNISSIBLE

~~

=

j 50 (116.50),

45 4[

35 3:

25 2 : %". j c,

35 N0ii:

THIS FIGURE VAllD ONLY FOR OPERATION AFTER APSR IlTHORARAL 3g

! ~ ( 0. C,'

20 4:

50 i:

100 120 140 160 150 200 220 240 260 280 300 F.c: Incer 25 50 75 100 0

25 50 75 100 innr 5 Bank 1 0

25 50 75 100 Bant 6 l

l l

1. i.

E.. - 'k. M. 2 9

Fig t:r e 3.5. 2 -4

. Rod Index Vs Power Level for Three-Pu=p Operatic:, O to 160 EFPD 110 105 (135.102)

(255.102) 100 OPERATION as 07 m an!D SD E5 OPERATION RESTRICTED 80 75 70 SHUTDOWN LIMIT (232.64)

• s S0 N

55 E

(61.50) c

e. 0 4$

OPERATION 40 PE R M I S S I B!.E I

x 30 25 20 33 (9.15) 10 (0.10)

E

~

i(0.0) 20 40 SC 50 100 120 140 150 150 200 220 240 250 250 300 R00 Indet 0

25 50 75 I OC 0

25 50

, 75 100 Sank 5 Bann 7 0

25 50 75 100 Bank 5

. e.dec.: :::. M 2 9

Figure 3.5.2-;

Rod Index Vs Power Level for Three-Pu=p Operation, 140 to 310 EFFD 110 l

105 (187,102)

(265,102) 100 95 90 3PERAT10N NOT E 01ED ON W 85 RESTRICTED 80 75 70 LIMIT E5 (232,64) 60 55 (109.50)

.,. -,0 45 46 OPERATION PERWISSIBLE 25 30 25 20 15 (15,15)

IC (c,j g) a

~

~

,0,0)

(

c 0

20 40 50 50 100 120 140 150 180 200 220 240 250 250 300 Roc incer i

0 25 50 75 100 0

25 50 75 100 Eand 7 Sank 5 0

25 50 75 100 Bank 6

. 2.e.dre.: :::. <, 2 9

Figure 3.5.2-6 Rod Index Vs Power Level for Three-Pucp Operation, 290 to 345 EF?D 110 105 (195.102)

(236,102) 100 SS OPERATION g%

90 NOT ALLOWED s@

e5

@4 80

%ps 75 SHUTCOWN 7g LIMIT E5 OPERATl0N 60 PERMISSIBLE O

55 g

a. 0 (116,50) u 45 40 35 30 25 20

( 2 2,1 c NOTE: THIS FIGURE Vill 0 ONLY FOR OPERATION AFTER APSR I.:

WITH0RAWAL

~

10' iO,10'

{

e 0h i

i i

i i

i i

r i

i i

20 40 60 E0 100 120 140 160 180

00 220 240 260 250 300 Rea incex i

i i

i i

i i

i

• 75 100 25 50 75 100 0

25 50

!ank 5 Bank 6 0

25 50 75 100 Sank 7

e.tren '::. e. 29

vi 712tre 3.5.2-7 APSR k'ithdrawal Vs Power Level, O to 160 EFFD

!!O (6,1 02)

(27,102) 100 90 (6,92)

(38,92)

RESTRICTED 80 (0,80)

(30,80)

REGION i?

W 70 E::

I 60 l

a 15 50

')(100,50)

PERMISSIBLE 40 J=

OPERATlHG 30 REGION 20 10 i

g 0

10 20 30 40 50 60 70 80 90 100 APSR n i tna rana I, 'J t

' :, ;4', 2 9

.-a,--

Fig tre 3.5.2-8 APSR '*ithdrawal Vs Power Level, 140 to 310 EFPD 110 (8.102)

(27,102) 100 90 80

-( 0. 80)

(30,80)

RESTRICTED o

REGION 70

_E.

7; 60 E

a 50 (100,50)

PERMISSIBLE u

40 0?ERATING REGION 30 20 Af ter 310 ETPD, APSR's are withdrawn en 100%

10 -

0 0

10 20 30 40 50 60 70 SD 90 100 APSR.itnarawal, ti t.;

=t"

'l 29 i

I Figure 3.5.2 9 Core I: balance Vs Power Level, l

0 to 160 ETPD 110 RESTRICTED

( 18,102)

(24,102)

(-20,92) 1 (23,92) 90 80

( -2 0. 7, 80)

(31,80)

E 70 E:

60 c-E PERWISSIBLE a

50

( 50,50)

(47,50)

OPERATING

[

,,0 REGION c

c_

30 20 10 0

E0 50 40 30

-20 10 0

10 20 30 40 50 60 Ccr e irt.Da lance, 5 a

9

!ce.du.- 2. F,29

\\.

Fig u:n 3.5.2 - 10 Core I: balance Vs Pwer Level, 140 to 310 ETPD 110

( 15.5,102)

(24,102) 100 RESTRICTED REGION

( -19,4, 92 )

(28,92) 90 80

(-19,80)

(31,80)

=

70

.E 7;

SD

'e 50

( 50,50)

PERMISSIBLE (38,50)

?

40 OPERATlHG g

EEG10N 30 -

20 10 0

50 50 40 30 20 10 0

10 20 30 40 50 60 Core i 32 lance, G l

.D 6 7. d E E r. *. ).' e h

Fig tre 3.5.2-11 Core I= balance Vs Power Level, 290 to 345 ETPD 110 PESTRICTED

(-24.3,102)

(17,102) nEGION 100

( 34.1,92)

(13,92) 90

(-27,80) 80 (18,80)

.=_

70 E

i!

60 PERWISSIBLE OPERATING a

50

(-50,50)

REGION (35,50)

._~

Y A0 E

30 20 THIS FIGURE (All0 ONLY FOR OPERATION AFTER A?SR WITHORARAL 10 t

50

-50 40 30 20 10 0

10 20 30 40 50 60 Core imaa lance, 5

's

e.,1('.

29

+n dren :

RANCHO SECO UNIT 1 TECHNICAL SPECI FICATIONS Li=iting Conditions for Operation T:e five 220-kV transnission lines are not under,the direct control of the Rancho Seco station. Tnerefore, all five cannot be assu=ed to be available at all times.

However, extensive reliability and protective features are u:il.ized so-that the' probability of losing more than one source of 220-kV power fre=' faults is low. ~ By requiring that two 220-kV lines are in service, prior to startup, one circuit vill be ir=ediately available following a loss' of the onsite alternating current diesel power supplies and the other off site 220-kV line.

If there is a loss of all 220-kV re=ote connections, power to the -

safety features will be supplied by the diesel generators.

The 35,000 gallons of fuel stored in each storage tank per:1: operation of the two diesel generators for seven days.

It is considered unlikely not to be able to secure fuel oil fren an outside source during this tine under the vers: of weather conditions.

The f eur 125-volt d-c con:rol panelboards are arranged so tha: loss of one bus -ill no: preclude saf e shutdown or operation cf saf ety f eatures syste=s.

Duri ; periods when one plan: bat:ery is de-energized for test or maintenance, the associated 125-vol: d-c bus can be supplied f ree its battery charger.

Ia:h redundan: pair ("A" and "C", "3" and "D") of safety features actuation anf reac::: prote: ion 125-vol: d-: buses has a standby cartery charger in addition to the two bus ba::ery chargers.

Loss of power f ro= one battery charger per pair of redundant d-c buses has no significant consequence since a standby battery charger is available.

In af'.i: ion, each 125-volt d-c bus can centinue to receive power fron its respec; ve battery without int e r:.:p tion.

Suffi ien: redundancy is available vi h any three of the f our 120-volt a-c v :a1 power buses in service tha: rea:::: safe y is assured.

Every reasonable effer: vill be ade to =aintain all saf ety instrunentation in opera: ion.

Durin; periods of sta:ien opera:icn under the ccnditien of electrical systen degradation, as described above in Specification 3.7.2, the operating ' action re:uired is to start and run sufficie.: standby power supplies so as not to c:npr:nise the safety of the plan:. As seen in Specification 3.7.2, a time

's placed on operation during certain degraded conditions based en the

'd d

reliability cf the available power supply.

e..r.r

+. N II.G, section f l

l

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.8 FUEL LOADING AND REFUELING Aeolicability Applies to fuel loading and refueling operations.

Objective To ensure that fuel loading and refueling operations are performad in a re-sponsible manner.

Soecification 3.8.1 Radiation levels in the reactor building refueling area shall be noni -

tored by R15026 and R15027.

Radiation levels in the spent fuel storage area sh all be moaitored by R15028.

If any of these instruments become inoperable, portable survey instrumentation, having the appropriate ranges and sensitivity to fully protect individuals involved in refuel-ing operations, shall be used until the per anent instru=entation is returned to service.

i 3.8.2 Core suberitical neutron fluz shall be continuously monitored by a:

Jeas: rwo neutron flux monitors, each with continuous indication avail-able, whenever core geometry is being changed.

When core geometry is not being changed, at least one neu:ron flux monitor shall be in service.

3.8.3 A: least one decay heat removal pu=p and cooler shall be operable.

3.E.L During reactor vessel head removal and while loading and unloading fuel frc: the reactor, the boron concentration shall be =aintained at no:

j less than 1850 pp=.

l 3.5.5 Direct ce==unica: ions be: ween the control room and the refueling person-nel in the reactor building sha.i.1 exist whenever changes in core geome-try are taking place.

3.S.6 During the handling of irradiated fuel in the reactor building at least one door on the personnel and emergency hatches shall be closed. The equipment hatch cover shall be in place with a minimum of four bolts securing the cover to the sealing surfaces.

3.5.7 Isolation valves in lines containing auto =atic containment isolatira valves shall be operable, or at least one shall be in a safety fez:ures position.

3.5.8 When two irradiatef fuel assemblies are being handled si=ultaneously withii the fuel transfer canal, a minimu= of 10 feet separation sit 11 be =aintained berween the asse=blies at all times.

Irradiated fuel as-semblies =ay be handled with the auxiliary bridge crane provided n:

other irradiated fuel assenbly is being handled in the fuel transfet canal.

-LL Arendr,en: ::o. 29

RANCHO SECO UNIT 1 TECTI 1 CAL S?ECIFICATIONS 3.8.9

f any of the above specified li iting conditions for fuel loading and refueling are not =et, =ovement of fuel into the reactor core shall cease; action shall be initiated to correct the conditions so that the specified li=its are zet, and no operations which =ay increase the re-activiry of the core shall be made.

3.8.10 The reactor building purge systa=, including the radiation monitors, R15001A and R150013, shall be tested and verified to be operable i==ed-iately prior to refueling operatiens.

3.8.11 Irradiated fuel shall not be re=oved from the reactor until the unit has been suberitical for at leas: 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

3.8.12 No loads will be handled over irradiated fuel stored in the spent fuel pool, except the fuel asse:blies the:selves. A dead weight load test a: the ra:ed load will be perfor=ed on the fuel storage building han-diing bridge prior to each refueling.

Bases Detailed wri::e: proceduras will be available for use by refueling personnel.

These ; ocedures, :he above specifications, and the design of the fuel handling

'cuip= ant, as described in subsec: ion 9. 7 of :he ?SA?. incorporating built-in e

interi::ks a=d saf ery fea:ures, provide assurance that no incident could occur duri=5 :he refueling opera ions tha: vould result in a hazard to' public health and saf e:y.

If no change is being =ade in core gec=etry, one flux monitor is sufficien:.

This per=its maintenance on :he instruzentation.

Continuous mon-iteri ; of radia: ion levels and neut::n flux provides icmediate indication of an u= safe :::di:1:2.

The decay hea receval pu=p is used to =aintain a uni-fer: b:::: O ct:en::a:io n. -

The refueling boron concentration indicated in I;e:if t:a:icn 3.3.1 will be =aintained to ensure :ha: the more restrictive of the f:1;cwing rea :ivi:y conditions is =e:: -

1.

Ei:her a kef f of C.05 or less wi:h all con:rol rods removed f::= :he core.

2.

A boren concentration of 21800 pp=.

Speciliza: ion 3. 3.5 allevs :he control room r'erator to inform the reactor buildi:; perse::e; of any i=pending unsafe condition detected fro: the main con:re; board indicators during fuel covement.

The spe:ifica:ic requiring tes ting reactor building purge ter=ination is to verif7 :ha: these ec=ponents will f unction as required should a fuel handling a ccid e:: occur tha: resul:ed in the release of significant fission products.

Specifi:a:ie: 3.5.11 is rectired as the safety analysis for the fuel handling accide : vas based

:he ass =ption :ha: the reactor had been shut down fer 72 h urs and all 305 fuel pins in the he::est fuel assembly f ail, releasing all pa; a::ivity. -

m e e

8

R ANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS i

Limiting Conditions f or Operation R EFER E!C ES (1) F S AR, subsection 9.5

(_2) FSAR, paragraph 14.2.2.3.2 1

1 I

.. end:::: :::. 29 3-46 l

rat CHO SECO UhlT 1

)

TECHNICAL SPECIFICATIONS Design Features The principal design basis fer the structure is that it be capable.of withstanding the internal pressure resulting frem a loss of coolant-l accident, as defined in FSAR section 14, with no loss of integrity, In this event, the total energy contained in the water of the reactor coolant syste= is assuned to be released into the Reactor Building through a break'in the reactor. coolant piping.: Subsequent pressure

. behavior is deter =ined by the building volune, safety features, and' the conbined influence of energy sources and heat sinks.

5. 2. 2 Reactor Building Iselntion System Leakage through all fluid penetrations not serving accident-consequence-liniting systens is to be nininized by a double barrier so that no single, credible f ailure or nalfunction of an active component can result in loss-of-isolation er intolerable leakage. The installed dcuble barriers take the forr. of closed piping systens, both inside and outside the Reacter Building, and va' ious types of isolation valves.(2) r RITIRINCES (1)

?S!J. paragraph 5.2.3 (1)

?S;J.sectien 5.0.4 O

e L

e 5-3

RANCHO SECO UNIT 1 TECHHICAL SPECIFICATIONS Design Features 5.3' R EACTOR '

Soecification 5 3.1 Reactor Core 5 3 1.1 The reactor core contains approximately 93.1 metric tons of slightly enriched uranium dioxide pellets. The pellets are encapsulated in zircaloy-4 tubing to form fuel rods. The reactor core is made up(9J (2) 177 fuel assemblies.

Each fuel assembly contains 203 fuel rods.

5.3 1.2 The reactor core shall approximate a right circular cylinder with an equivalegj) diameter of 128.9 inches and an active height of 144 inches 5 3.1.3 The averaae enrichment of the ini tial core for Rancho Seco is a' nominal 2$ 57 weight percent of U 35 Three fuel enrichments are 2

used in the initial core.

5. 3.1. 4 There are 61 full-length control rod assemblies (CRA) and 8 axial por<er shaping rod assemblies (APSRA) dis tributed in the rea: tor core as shown in FSt.R figure 3.2-45.

The full-leng,th CRA concain a 134 inch length of s ilver-indium-caemium alloy clac with stainless steel.

The APSRA contain a 36 ineg3jength of silver-indium-cadmium alloy clad with stainless steel.

5 3.1.5 The initial core will have 65 burnable ooison assemblies with similar dimensions as the f ull-length control roes.

The cladding will be circaloy-L filled wi tn aluminum oxioe-boren carbice pellets and placed in the core as shown in FSAR figure 3.2-2.

5.3.1.6 Reload fuel assemblies and ro s snell conform to design and eval-

,cet exceec an equivalent theFSARandshal}#'.

uation describec in percent of U A reload core may also enrichment of 3.2 weight have burnable. poison assemblies with dimensions similiar to the f ull length control rods with materials as specified in 5.3.1.5. (4) 5.3 2 Reactor Coolant. System

5. 3,. 2.1 The reactor coolant system shall be. designed and constructed in accordanse with code requirements.*#

5.3 2.2 Th: reactor coolant system and any connected auxiliary systems exposed to the reactor coolent conditions of temperature and pressure. shall be designed for a pressure of 2,500 psig and a temperature of 650 F.

The pressuricer and pr urizer surge line sncllbedesignedforatemperatureof670F.g;0 5.3.2.3 The reactor coolant system volume shall be less than 12,200 cubic feet.

L e.dtt.: So 29 5-M em seeeDO+ w

• " 88M8D -

e

+

RANCHO SECO UNIT'l TECHNICAL SPECIFICATIONS Design Features REFERENCES (1)

FSAR table 3.2-1 (2)

FSAR table 3.2-2 (3)

FSAR paragraph 3.2.4.2 (4)

Cycle 4 Reload Report (5)

FSAR paragraph 4.1.3 (6)

FSAR paracraph 4.1.2 i

I Arar.dren: No.29 5..

• e>-

egy m