ML20137F964

Proposed Tech Specs Defining Operability & Surveillance Requirements for Auxiliary Feedwater Sys.Supporting Documentation Encl

ML20137F964
Person / Time
Site:	Rancho Seco
Issue date:	08/16/1985
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20137F947	List: ML20137F943 ML20137F964
References
TAC-61487, NUDOCS 8508270135
Download: ML20137F964 (150)

Text

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.4 STEAM AND POWER CONVERSION SYSTEM Applicability Applies to the operability of the turbine cycle during normal operation and for the removal of decay heat.

l l

Objective 1

1 To specify minimum conditions of the turbine cycle equipment necessary to I

assure the required steam relief capacity during normal operation and the capability to remove decay heat from the reactor core.

Specification 3.4.1 The reactor shall not remain above 280F with irradiated fuel in the pressure vessel unless the following conditions are met.

107>

3.4.1.1 Capability to sup,91y feedwater to at least one steam g?nerator from at least one of the following means.

l A.

A condensate pump'and a main feed pump, or l

B.

A condensate pump or l

C.

An auxiliary feedwater pump.

107><

The required flow rate is 760 gpm at less than 120*F.

3.4.1.2 Two steam system safety valves are operable per steem generator.

3.4.1.3 The turbine bypass system to the condenser shall have one valve operable or the atmospheric dump system shall have a minimum of 1 of 3 valves operable per steam generator.

3.4.1.4 A minimum of 260,000 gallons of water shall be available in the condensate storage tank.

3.4.2 In addition to the requirements of 3.4.1, the reactor shall not remain critical unless the following conditions are met:

3.4.2.1 Seventeen of the eighteen main steam system safety valves are operable.

Proposed Amendment No. 107 3-23 8508270135 850816 PDR ADOCK 05000312 P

PDR

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.4.2.2 When two independent 100% capacity auxiliary feedwater flow paths are not available, the capacity shall be restored within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or the plant shall be placed in a cooling mode which does not rely on steam generators for cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3.4.2.3 When at least one 100% capacity auxiliary feedwater flow path is not available, the reactor shall be made subcritical within four hours and the facility placed in a shutdown cooling mode which does not rely on steam generators for cooling within next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Bases The feedwater system and the turbine bypass system are normally used for decay heat removal and cooldown above 280 F.

Feedwater makeup is supplied by operation of a condensate pump and main feedwater pump.

In the event of complete loss of electrical power, feedwater is supplied by a turbine driven auxiliary feedwater pump which takes suction from the condensate storage tank. Steam relief would be through the system's atmospheric relief valves.

If neither main feed pump is available, feedwater can be supplied to the steam generators by an auxiliary feedwater pump and steam relief would be through the turbine bypass system to the condenser.

107+

The auxiliary feedwater system is designed to provide sufficient flow on loss of main feedwater to match decay heat plus Reactor Coolant Pump heat input to the RCS before solid pressurizer operation could occur.

The requirement for e

two steam system safety valves per steam generator provides a steam relief capability of over 10 percent per steam generator (1,341,938 lb/h).

In addition, two turbine bypass valves to the condenser or two atmospheric dump valvcs will provide the necessary capacity.

107+

The 250,000 gallons of water in the condensate storage tank is sufficient to remove decay heat (plus RC pump heat for two pumps) for approximately 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

This volume would also allow hot shutdown for approximately 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> with cooldown to DHR system changeover at 50F/hr. (1)

+

The minimum relief capacity of seventeen steam system safety valves is 13,329,163 lb/hr.(2)

This is sufficient capacity to protect the steam system under the design overpower condition of 112 percent. (3)

REFERENCES 107+

(1)

B&W Document 32-1141727-00, " Heat Removal Capability of SMUD CST,"

March 1984.

(2)

FSAR paragraph 10.3.4 (3)

FSAR Appendix 3A, Answer to Question 3A.5 Proposed Amendment No. 107 3-24

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.8 AUXILIARY FEEDWATER PUMP PERIODIC TESTING Applicability Applies to the periodic testing of the turbine and motor driven auxiliary feedwater pumps.

Objective To verify that the auxiliary feedwater pump and associated valves are operable.

Specification 4.8.1 At least every 92 days on a staggered test basis at a time when the average reactor coolant system temperature is >305"F, the turbine / motor driven and motor driven auxiliary feedwater pumps shall be operated on recirculation to the condenser to verify proper operation.

The 92-day test frequency requirement shall be brought current within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the average reactor coolant system temperature is >305"F.

Acceptable performance will be indicated if the pump starts and 107>

operates for fifteen minutes at the design flow of 760 gpm.

4.8.2 At least once per refueling interval:

1.

Verify that each automatic valve in the flow path actuates to its correct position upon receipt of each auxiliary feedwater actuation test signal.

2.

. Verify that each auxiliary feedwater pump starts as designed automatically upon receipt of each auxiliary feedwater actuation test signal.

4.8.3 All valves, including those that are locked, sealed, or otherwise secured in position, are to be inspected monthly to verify they are in the proper position.

4.8.4 Prior to startup following a refueling shutdown or any cold shutdown of longer than 30 days duration, conduct a test to demonstrate that the motor-driven AFW pumps can pump water from the CST to the steam generator.

3 Proposed Amendment No. 107 4-39 J

o:

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Bases The quarterly test frequency will be sufficient to verify that the turbine / motor driven and motor driven auxiliary feedwater pumps are operable.

Verification of correct operation will be made both from the control room instrumentation and direct visual observation of the pumps.

The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant System can be cooled down to less than 305 F from normal operating conditions in the event of a total loss of off-site power.

Each electric driven auxiliary feedwater pump is capable of delivering a total 107>< feedwcter flow of 760 gpm at a pressure of 1050 psig to the entrance of the steam generators. The steam driven auxiliary feedwater pump is capable of 107>< delivering a total feedwater flow of 760 gpm at a pressure of 1050 psig to the entrance of the 3 team generators. This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 300 F when the Decay Heat Removal System may be placed into operation.

107> The auxiliary feedwater pumps are tested to verify they automatically start as designed upon receipt of each auxiliary feedwater actuation test signal. At least once per refueling interval, the auxiliary feedwater pumps are started on the loss of four Reactor Coolant Pumps signal and also on SFAS initiation.

The monhtly surveillance test demonstrates proper auxiliary feedwater pump

< response to a low main feedwater pressure signal.

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l Proposed Amendment No. 107 4-39a

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AND THEREL ARE NO OUTSTANDING NCR'S' WHICE. AFFECTTHIS ECT SDC IS' TO' ' COMMENCE CLOSING OUT THE ECE, 'IS PLANT WORE COMPLETE

" YELLOWS" TO THE STICKS.AND PROCESS' IF APPLICABLE

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• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • A

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.scsica ve e.suruxu :u.a r.-c.-

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o CfSCRIPTION:

Add safety grade indication of auxiliary feedwater flow to each steam generator and arovide AFW flow indication in the Control Room.

NCR ECN A-3622 Rev. 1 DESIGN BASIS REPORT REQUIRED:

Yes C No C NUMBER OF PAGES (w/ attachments):

SAFETY ANALYSIS:

SAFETY ANALYSIS (w/ attachments):

PAGES.

The change will provide dual flow rate indicators for each steam generator, thus a single failure will not eliminate indication for a APA piping train.

This change improves the

apability for monitoring AFW flow.

A technical specification change will be required and a post implement tion. review is required by NUREG 0737.

N)[

k 9/Wes x

/A/N/N Licensing Engineer Date Manacer Generation Engineerino Da t_e PRC RECOMMENDATION:

50.59(a)

Yes @

NoO 50.59(b).

Yes No O

~

DISPOSITION OF PRC:

her k6 n' e fN&

e a.

Unanimously recommends proposal $

MSRC review prior to implementing C e.

b.

Send to MSRC for concurrence 3

f.

Test of systsm required d

c.

ModificationsRejected Q

g.

50.54(p) review recuired Kg f.ReturntoCognizant' Engineer C

(gg[

g/gg PRC Chairman

'Oate

(

ATTALYSIS:

50.59(a)

Yes @

a.

Recommend to Proceed 15 Yes C No No O b.

Refer to MSRC 50.59(b)

Yes c.

Test of system required No C d.

Modification rejected C

(Nbsh lO55 Plant Suoer1ntencent /

V Date MSRC FINDINGS:

50.59(a)

Yes C

'No C 50.59(b)

Yes NoC (If applicable)

DISPOSITION OF MSRC:

a.

Recomends proposal

]

d.

Return to Cognizant Engineer C b.

Send to NRC for approval O

e.

Modification rejected c.

Recomends not to proce_ed C ov.H WORK H AS MSRC Chairman ottN COMPLETED Date COMMISSION APPROVAL OBTAINED:

ON J g[ 151083 (If aoplicable)

Cate MSRC Chairman my -

L 4 WORK REQUESTS CCMPLETE AND YELLOW 8.

RETEST COMPLETE sWG 80CE)JrMt.55NTROL,

\\ WINGS ISSUED (if applicable):

(If applicable)

~~

t Site Cocument Controi Cate Suoervisor ingr. & Quality Controi Cate OVERALL REVIEW:

Plant moc1fication cnange complete.

(If applicaole)

Manager Nuclear Operations Oate

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F AC ElSl WITM EXISTt M G E OUIPM E N T.

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F AC E(S) WITH EXISTING ECUIPM ENT.

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SAFETY ANALYSIS FORMAT RANCHO SECO NUCLEAR GENERATING STATION UNIT NO.1 ECN A-3622 Rev 1 NCR Work Request DESCRIPTION:

Add safety grade indication of auxiliary feedwater flow to each steam generator and provide AFW flow indication in the Control Room.

REASON FOR CHANGE:

To meet the requirements of Reg. Guide 1.97 (to monitor operation) and NUREG 0737, II.E.~1.2.2.C (Safety Grade Flow Indication)

EVALUATION AND BASIS FOR THE SAFETY FINDINGS:

The change will provide dual flow rate indicators for each steam generator, thus a single failure will not eliminate indication for a AFW piping train.

This change improves the capability for monitoring AFW flow.

A technical specification change will be required and a post implementation review is required by NUREG 0737.

bU

@ The proposed change will not increase the probability of occur'rence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR 'or create the possibility for an accident or malfunction of a different type than any evaluated previously in the FSAR or reduce the margin of safety as defined in the basis for any Technical Specification.

SAFETY FINDING:

EThe proposed change does nce involve a change in the Technical S ecifications I

O r 2r

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t v.

2

.v.4i WORK HASK J

/ )'4 E ' O.-

7 BEEN COMPLETED N

('

ON JUL 151983

-b/

HANCh E*

Licensing Engineer

/

4 re g,.q Review Engineer fd b I m JAs)

Date

/o - / -A 2.

j p

umwas m 1

e DESIG;; LASIS REPORT ECU A-3 62 2 REV I

!CR M/n UORK REQUEET 104130 DISCIPLI:!E I & C DATE 2/24/92 I.

PURPOSE OF DESIGN CHS::GE:

The purpose of this design change is to implement the requirements of GUREG

0737, item II.E.1.2.2, auxiliary feedwater flo,1 indication anc Regulatory Guide 1.97 Table 2, Type D, Auxiliary or Emergency Fcediater Flow.

This is further defined in ::UREG 0737 II.E.1.2 Part 2 by stating that safety grade auxiliary feedwater flow indication is required to meet the 10CFR part 5?, Appendix A Criterion 13.

1.

Safety-grade indicaten of auxiliary feeduater flow to each steam generator shall be provided in the Control Room 4

2.

The auxiliary fee 6:ater flow instrument channels shall be powered from the emergency buses consistent with satisfying the e.aergency power divercity requirements of the auxiliary f eeducte r system set forth in Auxiliary Sytems 3 ranch Technical Position 10 -1 cf the S tandard Revieu Plan, Section 10.4.9."

7 II.

DESIG:i CRITERIA USED:

3 1.

The flow transmitters shall be Class IE and shall meet the requirements with respect to separation,

seismic, and environmental qualifications.

l I

2.

The power supply and isolation cabinet shall be Class IE and shall meet the r equirements with respect to separation,

seismic, ano environmental qualification.

i 3.

Signals to Centrol Room for indicgionvillnotbeIEin interim mocification curing theA-- r - ner 1992 outage, therefore, the indication in the Control Room is not Class 'IE and shall utilize existing non IE indicators c

and the computer for cisplaying the information.

\\

Conformance to aCREC 0737 uill be achieved when msjor control room modifications are implemented.

(

,w.4i VTORK HAS BEEN COMPLETED ON

.IllL 1 " 1 33 1

,H,ANC.H. O :m.U u c c m g,,

m,_

V -

4.

The following codes cnd ' standards are applicable, except as indicated in II.3 above, to flcu trans:. itter purchase

(~

and installation, power supply and distribution cabinet

(

purchase and installacion and cable and wire routing to the IE portion of the system:

Sconsor !!urber Subject IEEE 279 Criteria for 1:uclear Power Generating Station protection systems.

IEEE 323 Qualifying Class IE equipment for Nuclear Pouer Generating Stations.

IEEE 344 Recommended practices for seismic qualification of Class IE equipment for I!uclear Power Generating Stations.

IEEE 384 Criteria of separation of Class IE equipment and circuits.

IEEE 379 Trail Use Guide for Application of Single Failure

!!uclear Pouer Generating S tation Protective Systems.

i III.

CALCULATIG"S A!!D DESIGIT I!!FOR"ATICII:

1.

Installation, of the flou transmitters and the power supply / isolation cabinet meet the requirements of Class IE safety grade.

2.

Conduit and cable trays from the transmitter and power source to the power supply / isolation cabinet meet the requirements of Class IE safety grade.

3.

Each $f the auxiliary feedwater piping. rain will have redundant flow measuring ano indication devices to meet the single failure criterion.

, n.u WORK HAS BEEN COMPLETED IV.

FAILURE HODE:

ON JUL 151%3 An electrical failure of any chann el

( jpM1CHC~,MQQ failure short circuit or open circuit) will ISIILECgthTfp((1pLjlow R

rate indication for each au::iliary feedwater piping train.

The Control Room will be aole to ascertain the actual performance of each AR S train at all times.

(

A tubing failure vill result in the loss of flow rate indication of the damaged auxillary fecduater piping train.

2

V c.,'

,V.

COMMENTS:

4.,

The design meets the requirements of 10 CFR Part 50 Appendix A, criterion 13 and is in compliance with the requirements of MUREG 0737 and Regulatory Guide.1.97.

Design EngineeT A

Date b"

~bb f o. rzoumos Review Engineer [d Il7 w>h Date.I-h Al j--

)

U. d i WORK HAS BEEN COMPLETED

.ON JUL 1519S3 RANCHG SECO

.E.E_ _ DOCUMENT CONTROLg O

C

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SACRAMENTO MUNICIPAL UTILITY OISTRICT CFFICE MEMCRANQUM g-To:

R J Rodriguez /0 G Raasch marm July 22,1982

~

rnow

J J Mattimoe, MSRC Chairman AUTHORIZATION PRIOR TO 10CFR50.59 Sil8MITTAL FOR NRC MANDATED CL*dGES urcr Section 50.59, " Changes, Tests, and Experiments," of 10 CFR Part 50, " Licensing of Production and Utilization Facilities," requires the holder of an Operating Licensa to furnish to the Cemission a written safety evaluation when he desires to make a change to his facility involving a change in Technical Scecifications or an unresolved safety question.

NRC mandated changes (example:

NUREG 0737 modifications) fall in this category and must be preceded by a Technical Specifica.cion authorization. submittal.

This submittal consists of two parts:

the proposed revisions to the Technical Specifications and support documentation for the proposed changes.

The Quality Assurance Program does not pemit issuing a work recuest via AP-3 until the 145RC Chaiman has authorized work initiation via QCI No. 5 requirements.

The obvious impass must be circumvented or NRC mandated changes cannot ec=ence.

Limited work authori:aticn is to be used to initiate a work recuest to allow work to comence.

The work is limited to NRC mandated changes only and no tie-in to an operating system will be permitted.

Prior to the tie-in, the license change must be approved by the NRC.

cc:

P. Oubre' G. Coward

. T. Perry J. McColligan v

,,o work HAS J. Jurkovich BEEN COMPLETED ON JUL 151983 1h RANCHO SECO SITE COCUMENT CONTROL, j

'L

ECN No.

-M[2 Transmittal Oate 9-2,747 2 PACKAGE COVER SHEET To:

SDC (M/S 255) To:

f_7 This Package Is Complete, Transmit To:

bb d hH Nuclear Operations Designated Engineer g The Major-0BR is complete, please attach copy to this package.

g This Package Is Not Complete, Proceed with construction subject to conditions given in Attachment No. 2.

f_7 This Package Is Not Complete, Hold For:

h.[Wed FROM:

Cognizant Engineer The complete ECN Package is submitted for your review and coments.

Please review this package for the following:

Decision 04 Agreement with 10CFR50.59)naa tlve s uMrh s w d bre dd Testabil ity Trow.%s olo d5 fee whenc3 St'j*lcou/afto*3 M); n41Ng SNr-3 g

c Maintainability Nord Mt9.tt'7 pJfIMMM.we *%r f

Requirements w.sor n tamM l' Nv Traig,3 dt eqnf.fh o *> re9<'<*

"op so.

y If coments are no eived on or before (Date -

Normally Five' (5 rking days), this package will be rel+.asec oy 50C for construction. _ A 1 coments are to be attached to this transmittal sheet and returned to ADC.

.._,n, WORK HAS

/

-/,

BEEN COMPLETED

,/

Coments Attached ON ~ JUL 151c83 L7 No Coments RANCHO SECO Nuclear Operations Designatec iingineqally. pyhtet.J CONTROL _

Note:

If "No Coments" is checked and signed by the Nuclear Operations Designated Engineer, a signature by the Cognizant Engineer is Not required.

{

Coments have been reviewed by MCognizant Engineer and CCN oackage will be released for construction.

/

/

/d - /c) -@2.

Cognizant Date c WC bf b

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Transmittal Date 9-27-82_

The ECN documentation package is incomplete at this time.

The following items are incomplete:

Item Forecast Completion 10~/O'f2

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STOP Mci.hanical Lint.

Originator

.4 N.O. Deatsnated Lngr.

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C.E. Cogstaant Ennt.

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Design City Supv. Engr. M W

32 Q.C. Inspector Supw. Engr. N 32

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Dieterich. Licensimt Enge...

32 C. Coward, hcLear M.itet..

N5 215 R. Lawrence. Sr. Mcch.

Engr.....

Maryellen Kruger..............

.............. 233

.e This ECN issued by SDC for documentation preparation 3

tCNiDCs CtOSE Oc CuECxt.rst only..

ON SY 1.

All yellow DCN copies made for stick files ORICINAI. ECN HELD AT SDC L*,NTIL alt. *X)CUCTA!!DN IS COMPLETE A.ND ALL WOKK CC"PLETE DCN TRE SM1!TAL PACK-2.

All ECN and DCN transmittal ACES HAVE SEEN CO."PLETID.

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2 THIS COPY T0:

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N.O. Desig. Engr.

STOP C.E. Cog. Engr.

6tL M 3 Originator _

Originator N.O. Designated Engr.

hp Supv. N r. C Supv Enge. E

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208 R.

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Supv. Nuclear Maint. C. Coward....

275 J. Hergon.......

Plant Superintendent. P. Cubre'..........

200 J. 'Jurk vich..

200 Tech. Support. D. Whituy.

1. • *D "************

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J DATE Accounting J. Vance.

2i5 THIS ECN W!LL NCT AFFECT rnC Secretary..

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Plent change (s) was authorized by the attached ECN and implemented through those DCN Transmittal Sheet (s).

drawing changes listed on the correlative Purguant to the Rancho Seco Configuration Control Procedure, ECP-1, paragraph 4.7 you are to review those plant procedures for which you are responsible and initiate chrnges that are necessitated by this plant modification.

9-REVIEUER'S TI. EASE ll TNTTTATS l ROUTE TO:

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DATE SEST 7-)[-[3 BY m'-

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All yellow DCN contes sede for sttet files.

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ECN No. A-3094, Rev. 2

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ENGINEERING CHANGE NOTICE P r***'" *v

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K. J. Varma 9-28-82 1

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@ THE FOLLOWING SYSTEMISI WILL BE AFFECTED SY THIS CHANGE gp Auxiliary Feedwater System qv R. P. Wichert l 0 -F-P2.

Nca s

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@ REASON FOR CHANGE To improve the reliability of the Auxiliary Feedwater TTPE ECM e

system per cormiitments maae in tne utstrict's vecember n.a m won eri sus a 6/,

63/s teller to Lne HKL (flaLLimoe to MelG).

9

@ DESCRIPTION OF THIS CHANGE PRoveOE A OETAeLEO DESCRIPTf 0M AND ITS APPECT ON PLANT OPER ATION. INCLUDE SMETCNES AMO OTMER PERTINENT IMPORM ATION TO COMPbETELY DESCRIES AMO ILLUSTR ATE NOW CM ANGE IS TO FUNCTION AS WELL AS BLLUETR ATE INTER.

P ACEIS) WsTM Ex sSTING E G ulPM E N T.

IM O4C ATE WN AT NEW C O M PO N E NT(S) ARE R E Gut # E O. OR AWINGS APPECTED AND ESTIM ATED M ATE RI AL COSTS.

The Auxiliary Feedwater (AFW) Pump test line will be relocated.

It will run frcm the AFW crosstie line (between the crosstie valves) to the condenser i

hotwell. A 3" pneumatically activated control valve will be installed in the line. This valve will fail closed whenever either of the AFW receives a " start" signal from EFIC. Connection to EFIC will occur under a separate ECN.

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A flowmeter (QA Class 2) will be added to the test line to improve testability.

Drawings Affected: f4-532, Logic Diagrams, Isometrics, Support Drawings, Vendor Drawings, Raceway Drawings, I-Drawings Cost: flaterial - $200,000 PLANT WORK HAS

$20,000 BEEN COMMED Labor Engr.

- $100,000 ON Aug - 125 ~

RANCHO SECO

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X PLANT WORK IS' CCMPLETE AS DESCRIBED IN EXISTING.0CN TRANSMITTAL PACKAGE (S)

AND THERE ARE NO OUTSTANDING NCR'S WHICH AFFECT THIS ECN. 50C IS. TO' COP 9 FENCE CLOSING' OUT THE ECN,. ISSUE PLANT WORK COMPLETE " YELLOWS" TO

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ENCLOSURE l4.6

{

ECN RELEASE FORM' iSTATION/0WNEA ECN NO.

UNIT NO.

SNEETS RANCN0 SECO NGS/SMUD 3094 Rev.2 1

1 of 1 AUXILIARY LEE 0 WATER SYSTEM TESTING ST'ATUS No Testing Required.

6~

( d MEL Sheets Substtted QN //l$

kN

/

NO F

(.

h

/ Start-Up Engineer Date t i e.n.

[ ] E.T.

.n.'

Yk

% WZ7/h([

Start-Up Supervisor (/ /

Date i

RELCASE ACCEPTANCE s'1A -

RELEASE REJECTION REMARKS:

f

~

~ $" $b h

/

SMUD, Nuclear Operations Date l

l Rev. 6 k

h AP.44-14 t

W A

(

REVO 0F PROPOSED 50.59 FACILITY C I 1E Log No. 33i D

l.t D$SCRIPTION:

Install flanges and orifice plates on lines '1"T-A"-n" w ' ' " ' ^ "-D B 2.

Relocate the Auxiliary Feedwater (AFW) Pump test line.

EcNPLA852WORENASstal. the r

flow transmitter and controls.

BEEN COMPLETED ON AUG - 1 $85 NCR ECN A-307% b.L RANCHO SECO SITE DOCUMENT CONTROL DESIGNBASISREPORTREhuIRED: YesC NoC NUMBER ur rwacs (w/ attacnments):

2.

SAFETY ANALYSIS:

SAFETY ANALYSIS (w/ attachments):

PAGES.

i This change will provide safety grade indication of flow to each steam generator.

The changes are quality and seismic Class I.

h'd

&@z aA nkelsv

/

Cate Manaaer Generation Enoineering Date Licensing Engineer 3.

PRC RECOMMENDATION:

50.59(a)

Yes@

NoC 50.59(b)

Yes@

No C be be v-DISPOSITION OF PRC:

he<

M et mot MSRC review prior to implementing C a.

Unanimously recommends proposal @

e.

b.

Send to MSRC for concurrence

f. ' Test of system required M

c.

ModificationsRejected C

g.

50.54(p) review recuired d.

Return to Cognizant' Engineer

[

lp jg g{

ORC Chairman Oate b ANALYSIS: 50.59(a)

Yes[

Y h es C No a.

Reccmmend to Proceed No C b.

Refer to MSRC M

l 50.59(b)

Yes c.

Test of system required q

N d.

Modificat n rejected C

% fg f.T.gg n JJN ffGNs Av'rMo M ffit

/.L / V Plant Suoer1ntencent

/

Otte 5.

MSRC FINDINGS:

50.59(a)

Yes%

No C 50.59(b)

Yes@

NoC (Ifapplicable)

DISPOSITION OF MSRC:

a.

Recomends proposal 3

d.

Return to Cognizant Engineer C e.

Modification r -

ted C

b.

Send to NRC for approval g, 7ph gg Recomends not to_ proceed _ C gy

~

u Date c.

RSRC Chairmfn 6.

COMMISSION APPROVAL OBTAINED:

(If applicable)

Date MSRC Chairman 7.

ALL WORK REQUESTS COMPLETE AMD YELLOW 8.

RETEST COMPLETE AND ACCEPTABLE:

DRAWINGS ISSUED (if applicable):

(Ifapplicable)

Site Document Control Date Supervisor Engr. & Quality Centroi Ca tT

(.,

OVERALL REVIEW:

Plant modification cnange complete.

(If applicable)

Manager Nuclear Operations Cate 10..

C0CUMENTATION COMPLETE:

Ouality assurance Diracter Cate

/%.

.0 Log No.

335 g

1 SAFETY ANALYSIS FORMAT.

RANCHO SECO NUCLEAR GENERATING STATION UNIT NO.1 ECN A-3094 Rev. 2 NCR Work Request DESCRIPTION:

Install flanges and orifice plates on lines 31821-6"-DB2 and 31823-6"-DB2.

Relocate the Auxiliary Feedwater (AFW) pump tcsc line. ECN A-3622 will install the flow transmitter and controls.

REASON FOR CHANGE:

To improve the reliability of the Auxiliary Feedwater system as committed in our December 17, 1979 submittal to the NRC and to implement the requirements of NUREG 0737, item II.E.1.2.2.

EVALUATION AND BASIS FOR THE SAFETY FINDINGS:

This change will provide safety grade indication of AFW flow to each steam generator. The changes are quality and seismic Class I.

PLANT WORK HAS sten COMPLETED ON AUG-11l185 RANCHO SECO SITE DOCUMENT CONTROL

@ The proposed change will not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR or create the possibility for an accident or malfunction of a different type than any evaluated previously in the FSAR or reduce the margin of safety as defined in the basis for any Technical Specification.

SAFETY FINDING:

O The proposed change does.ae4 involve a chagge in the Technical Specifications R4pred dug.Edr.07 Y).

^

" : '- t; N., m.

Licensing Engineer d 2w NL

//d4!Rv Date

(.-

Review Engineer M[

Date /'

c/8 L

/

/

SMUO4913 9/80

~

m DESIGN BASIS REPORT v

ECN A-3094 NCR N/A Work Request 10430 U'

Discipline Mechanical Date I.

PURPOSE OF DESIGN CHANGE:

The purpose of this design change is to implement the requirements of NUREG 0737, item II.E.1.2.2, auxiliary flow indication.

II.

DESIGN CRITERIA USED:

1.

Material to be Quality Class I, compatible with existing boundary material.

2.

Design configuration shall be analyzed to satisfactorily withstand a Seismic Category I event.

3.

Flow resistance resulting frcm flow orifice installation shall be analyzed to show no adverse effect on ability to supply auxiliary feedwater to the OTSG's at the required flow and pressure.

4.

Piping will be installed to SMUD drawing M-870 and ASME Section XI, class 3.

III. CALCULATIONS AND DESIGN INFORMATION:

1.

Dead weight, thermal and seismic analysis is acceptable '(see attached).

2.

The addition of the flow orifice will result in 157.6 inches of H O 2

pressure differential across the orifice at a flow rate of 1,000 gpm (see accached calculation). This converts to a 13.13' TDH/5.7 psi loss across the orifice.

B & W Doc. ID No. 15-1120580-02

Title:

System Description Auxiliary

.Feedwater System requires a minimum flow of 780 gpm to one or both OTSG at a OTSG pressure of 1050 psig.

The (attached) AFW system resistance curve indicates a line resistance of 75 ft. at 780 gpm.

The flow orifice resistance at 780 gpm = dP2=dP( )

1 AP2 " 13*13 (1 0)

Pt. ANT WORK HAS D

dP2 = 7.98 ft TDH ON Ayg - } gg$

! (#

RANCHO SECO SITE DCCUMENT COP (rRot.

---

y

r-f i

e f,.

Total resistance = 75 + 7*.98 = 83.0 f t TDH @ 780 gpm.

The minimum available TDH @ 780 gpm is 2700 ft. TDH from P-318 (see attached pump curves).

2700' - 83.0 ' = 2617.0 ' TDH available for delivery.,

2617.0' TDH = 1130.0 psig Therefore, the line can supply 780 gpm to the OTSG at 1133 psig.

l This is greater than the minimum required. This calculation is conservative because the (attached) curve indicates that a flow orifice with a 8 of 0.76029 will result in a 42% loss of the actual dif fereritial.

XV.

FAILURE MODE:

1.

The configuration has been analyzed to withstand a Seismic Category I event.

(See attached report).

I V.

COMMENTS:

1.

Installation will be done in accordance with applicable approved proc edures.

2.

SP-210.01 A and B must reflect increased pressure drop.

Design Enginee bND h.

Date

~

f cu-Date / O ~~N Review Engineer -

~

gineer D, ate PLANT WORK HAS BEEN COMPLETED ON AUG - 1 E85 RANCHO SECO SITE DOCUMENT CONTROL.

Ms. Qu[7Hegn M %Qic W$U

~:-

~

Bechte: Powe.- Corpora' ion E ; ++ - C: r.:*: t

~20* Ea:

e r

..1.

/

N O A n C a ',m.a 9Cii"

w.. at:n tt

• e:. vu-

r.....we..:r.s:t.tt :....:. a

't.43-:.t. : us -

April.10, 1980

. Letter-No. BSt-1063 F. C. Lavrenet 7.pn:h: Se:: Prlj ect Engineer Sa;ranente Municipal Utility District T. O. Sex 13!30 Sa:ranen::, CA 95313 Subdect: Rancho Seco Nuclear Generating Station, Uni. #1 Bechtel. Job 12334, S?.' 3 TasL563 Stress Proble.s 80A and 91 Auxiliary Teed. rater Lines Filer D.02 and D.03 i

Dear Mr. Lavrance 3

Dead weight, thermal and Seis=1e Class 1 analyses have been carried out'on the "As Built" configurations of the. Auxiliary Teedvater Lin'es.

~

h These analyses included the new o%1fice-with its flanges, one in each feeteater line.. It was found char they met all. code requirenants without requiring additional supports or modifications.

Very truly yours,.

BECHTEL POWER CORPORATION D. C. Philp Project Engineer Los Angeles Power Division DCP:TIW/evl ec:

R. Wichert l

B. Stiver g

l 6

L. Smith.

sg bec:

A. T.'Cu= mins F. E. Webb j

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O M ffpWRATE CALCuh04 SACRAMENTO MUNICIPAL UTILLTY OlSTRICT [ ornerwcuanANDUM A To: ' Lloyd Steph'ensort.- DATE: September 28,.198T s .f ~ EQW'Si-46%. h ~ ~,. l. c -

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~ ~- * * ~ ntoup Ectr Wichert< p - - - ~ .s - CUBJEcn AUXILI ART :EEDVATER FLOW. METEK ORIFICE P.ATES AND FLANGES .u.

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'^ .. - :t. The orifica plate-flanges purchased. for the Auxiitary Feedwater-Flowmeters in.1971 are: currently irr the "A" Varehouse at Rancho. Seco. They are equipped with flange-tsas and are complete with ~ proper certification to alicw their use in the. Auxiliary Feed-water Line ~ ,c 1 ~ ";. The orifices purchased. for' thei above mentionedf franges are also - .l Trr stack; in the "A" Varehouser at: Rancho Secc They have art. instde drameter'of 4. 380 inches /f+.3&T inches respectively.:. This fastde diameter results. in a Keta ratic of.76017 Using-this. Beta racic, it cart be cal.cutatedschat fait scale pressure: differ-- entlar of-T 57.6. inches.-oFwat'er weir ccerespond to a. fulI scare ~..... fiow. rate of I,00G gal Tons p{reinute.- ?~

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• M PtANTWORK HAS-f BEEN COMPLETM y g,t Q

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'~ succcr, ; e ric.Tuw AFL./ Flow Ccem oer!T-oETl.c!. x\\Mchem REFERENCE' t ( av - f. ACTDAL Flow COGFFicIEMT For c O(bRCG PC.hTES. Ac3 DEG!v&R.GD (3 = 4. 5 6 0 / C 7 G I . 7 6 0 2. 6 7 ah- \\\\00 ml / 90 *F 1 7 g-Gz.for ib-/rP ,se. . S't C < t c ~ ~' %,1 FF - s _ =. ~ fa

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[. 1 1ZS(4) $1.h _gf,hgq I' Q V 1T {-TGC77]T)k55$CD6f .(' lb 0b.Y5 S09 .bb']O . ST C * \\ 0 '

• PLANTWORK HAS

9'r!l 5 7 6. 6 h BEEN COMRETED ON AUG -11985 lie * '. 717 N O W

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~ %sMun SACRAMENTO MUNICIPAt_ UTILITY ~ DISTRICT . p.,. ,f ,e n oATe N. susaEcr 7. lkUON hKi Piaw Cc$IOef c'"y k _ R3PEMENCE \\. b.)zc.Ven. 7. I c .a9?iatl597776 I VH.MO I,.000 5 nu i / c- -l t jf0b. I-[76065)' / i x ~ = UT8 0 N's - c+I hv = E'ZT7.my O (@ 66T) e.c _ m..de.x A. .gtl5p;,A:..-g;! g^n G. - e-7 PUNTWoRK HAS-I.. %{ .100 gacs,7 %..c. ~ 7-:0 assacoueumso fv 3=61.C b M on Aus-1ses I M = sb m 5~ G/p.s uncaoseco sneoccuusarconTaot L - I. Coo o \\l = LL19'kW 9d .1l.19 34 (.7607 9if,'l20o*])t{b 2.f ~ . (,fy/o 3 7 E 969.67 = \\le-. 737lH O R = E653.906 0 b =.730ro( c-K- ..%3 ( 'W C, .596t99 ,. p %-=,-.

9 g esuun SACRAMENTO MUNICIPAL UTILITY OlSTRICT g .c. i QATE m 7'LT4/ \\ SU5 JECT (ch;ucJ kPL/ Piau C' cM~ eieg g g, l I a =f *a a= Q ggd / 3 .D99 TOE lCYcV Fw )\\ hu ~ ~ cc = c 8 4 1 ._ 3 \\ 4 i, ( j -t / q=?.1I60 [f.r ~ nu \\57,7T i

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\\5T5T in HzcE l: EGuhL L (000 me-C s;Y =^ - J y; - n-PLANTWORK HAS BEEN COMPLETED ott AUG-11985 RANCHO SEdQ SITED 0CUMENTCONTROL -:b 4 4 9"-E .-,--~ _, n -~ -

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p,_s,. e . SACRAMENTO MUNICIPAL UTILITY DISTRICT OFFICC MCMORANDUM ^

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ig. _ 1; D^m [ ecenMO#W6RhAs ~ To: Jim Field

..BEEN COMPT.ETED

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• 3.

Bud. Beebe . j- . c. .J'/ ruou: ({- S&TEDO U CO TR duoxcr: AR1 FLOM RATE - ' =\\ Thfs memo summarizes the expected Auxiliary Feedwater Flow Rate ~ ' to a Steam Generator for various ARI pump and S/G pressureThe val combinations. g '* ~ inforr.ation calculations by B & 11 Lynchburg (SMUO-81-040,and March 17,1981) All values of system resistance assume the control valves are Condensate storage tank. is assumed to be full and -2. wide open. 0 at 20 C e. g i , Since some of these fTcws are in scess of the 165G gp::t max mum allowed under the ARL System Descciption, we should assure Cb ourselves that they represent eitlier non-credible cases er alter It should the syste:2 or controls to preventithect frc:n-occurring. also be noted that.for the low pressure cases, the arf pumpsNPSH would be at runaut. pumps at these floss have not been checked by me. S.G. S.G. Ringheader l Injection Press. Injection Velocity (ft/sec) Flow (gpm) (PSIG) i , --2 s 2.8 One ARI Pump /one S.G. 1020'psig 940 600 psig ~1260(runout) 3.8 ~ ~ ~ 0 psig ~1260 (runout) 3.8 4.5 . 2 AFW Pumps /one S.G. 1020 psig 1500-7.2 600 2360 2520(runout) 7.6 0 If you have questions on the basis for the values, e'tc., please let me j ' know. L J. Y. McColligan t.. H. Stepbcnson f()Mf.(()gyg5 cc: R. Wichert ^ ^

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~.& g CALC.ac LATION.rio,.S H El._1 U <=-.a=- qJf7 rcu com ,,.: r=:=.. ep a c. b / 2- - CHECKED DATE >'e'M DATE s:cnAruRE S/Mb D ~ S IAI f--S Jos na 5 2 92-pgo;ter Aox-F e e n R > n i t. P--3t ? / P- ?rr / G sueg7 o guegrg SU31ECT o8.scerltics : 70 liggiey T.-es~tGid GnTdnelsor Aux /uney FrrD TMJMPS' 7-31g + P-ci7, sas50 su Exts7ilJG P' Pins ~ BAC.kSECYDD : RAI CydMGED, MCEE [iNCE

1970, PIPIUG LAYCOT. '

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(cc +) th ) (i 2,,1)

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n. H ,g,; h h s CALCULATION SHEt : r e -.c = ' - macar si. co n eon atio n wo"*II.'~c1*f2/o'd"wsm 'h s!CNATURE DAE CuECKED kMDAE O D M IO !! 2-bPROJECT O JOB N0 su81Lg 20%, M 5D MMP.T $7/7 d P Dr sneer C~ Or /W sue n 16bH JueL =..?r-2st. hMI.' -KucTron HU -Nwon 'hgor.47-W5=~2N,ot&51 12 E E 4 ) c WM AW-IL= _.i+,7(2:5f)+ l 716 7 -2.2.7 .4T8(2,7)) i ~ = 13,7 22.- 2 /C-h 59 =~ 26,14 FT' ~' .&f: /& N r ut grottteer - i.s P7- .i. 5 ~ N PSIf IT11A*G13= *Z3 T -15 '" lo o & Pi. j. ~. ?! ptANTWORK HAS ~ m BEEN COMPLET. ED j 7, t f~', g ' g-15 h..1 ~, L 9. . ~. RANCHO SECO sn'EDOCUMENT CONTROk i i F l \\ l t l i .i i I i - i ....,...t.. - 'j r '. t g c s I 3! I. l s. q l t r .I I

. ~ -. g CALCULATION SHEC] . = =c,;;;r c=c"m-gryLAm** t vna. enaw.a I4 Of- 'YE '"" C DAir /6-26 '7I-CHECKED DATE // !~IM I , cicnATURE l'*naster s w ct i) - UM/G T ica no an OF l5 SHEETS U Y b ~5 E f) #UNYS ; ?~ II5 ?*II'/ ^ SHEET SU8 JECT _ ~ OrscWi[EG6~ 3 mow (/ 6) -(t). Fort F-3f7 ptsctfMt.GE CIntrs 3 t 72.0, 5i121, si s z.6, 3 i s2.1 - G'L oh7Z SCH 80 S .'C D. = $~% / "~ = 0 480 / W m y.) sea cow u mo Arc cEA)G77./ = #S7 P r. (fen 9) m y_g y ft 77/^!G3,5 YAl VES (KER Sh

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== Assarte r'cocu fe'cM O8.) to (/d) 70 86 76o' GFt/, 3/Ncf P//'F EGCI/Va i 4:'iU $ 7"A' f /3 26*C//t!t/&~C-Y SHOM*1~ /]MO t// W $7 fli'~C- /// j;~CC ts.) / C A/d7'.54(d.CTMou7"//}ll, llGTOCIT'r' DfFF&MC'/C O~ ! I opcy / Ps/sec. I g/ .g n=T-n&- HW.} F7go GAL /,11:./. ~ '_ 9 y FTQ ' SEC.-Gt1L. _ (5, qs l,y.) ' h" \\/ =(-T.&O Mfec.)* /. 4'3 FT. Zf

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o 'a CALCULATION SHEE SCCM Eb..C.ORPo n.. Art O#4 Y / M DATE #/ M 6M C OAir//~b CHECKED pnATURE ~ MI JCS NO-M iROJEct_ b N /7 -/ n? O sua$fi y /~A=Md felisWT~ f-\\/R /X?ISI SHEET ~

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SUBJEC, og suEErs 1

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@ ALCULATION SHEET @ I' i DA E / CHECKED DATE SIGNATURE ' Pao;Ecr S/t/ 6/D - /TA/65 YE aos no-M SUBJECT SHEET OF SHEETE i t %v),- Y Of* i ~ s -O 6P ~ (f'T*'IY'I) f OGJ~ Is7) -2.2 Fr. 4-Z 430 Pr = ZGrl5,8 M~ l r d8* //30,

1. .5 /

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=., - f M ~ THE B'ABCOCK.&. WI COX C0t NY POWER GEllERATIOil GROUP p'N l J. A. MIDDLETON, RESIDEriT EliGItiEER. - SMUD Fro: sos us.s. G WEATHERFORD ASSOCTATESERVICEMAtlAGER ( FiIe No.

Cust, or Ref.

SMUD Subj. Date MAY 17,1979~ i 'MAXIMuti FILL RATE ON AUX FEED _ SYSTEK ! i j m...... ...~.... t. This letter confirms my telephone caIT to you on May 16, 1979 stating that -i a fill rata of greater than 500 gper but Tess than 1000 gpm was acceptable f E have confirmed with througfr a. single OTSG. auxiTiarf eedwater header. P. A. Sherburne/ Component Engineering that.the limiting-fTow velocity across A fTcw rate OTSE tubes in the auxiTiary feedwater header regiorr is 5 tr/sec. of 5'.5 X 10* lb/hr/0TSG wi1T not exceed. this velocity limit. Thfr flow rata corresponds to a. mcximunrfiTT rate of: T100 gallons per minute Therefore, the 1000 gper fill rate inaximunr,. requested by SMUD, is acceptable. d~ If you need. further assistance, pidase-advise D, g, _LGW/hh cc: JT Janis PA Sherburne as-in I Y?C .gnoo l r 1 j e +_.,y,,e

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i SACRAMEN' O MUNICIPAL UTILITY DISTRICT oFMCE MEMORANDUM + O JohnMcColligan[j7gja,-M oATE: June 8, 1984 To: I rnoM: Dave Abbott cuaJacT: OPEN ECN STATUS LISTING The following lists current status of those ECN's for which the Mechanical Group has prbaary responsibility and for which information on the May 3,1984 ECN ctatus list must be updated or corrected: h0ftQ A-3500 ECN voided but shown open on 5-3-84 status list. c A-38923 Will be formally reassigned to C. Appel to reflect current rapponsibility. a.7s,.N9,y,,a/ O <- Bryef, qf,wjp g, [//, b, (.3.v, -A-4015 Awaiting. receipt of dampers; DCN package prepared. Qi_c, A.s.,(cf -b :&.:. s..t v.:,. it.s. \\ %Qv..C a..a. A-4615 Study in' process; if required, earliest possible installation would be during 1986 outage. h" A-4708 Investigating necessity for DCN's; work requests still to be initiated;. outage not required. ' O,q - M Original ECN reportedly sent in early 1984 to Mechani \\ Group; \\OttLAAAECN probably not received; ECN can be closed. -15 0 M w t d. Q \\- 4 W T 4 C A-3920 1984/85 outage ECN. 3920A, B & C now reassigned to

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g Approved for 1986 outage installation, e/ty)new*sg on ['!. A-3497 A-4102C 1984 outage ECN. MaH< regu+s7.: /1so n/,wo e /< ja, fsop :, i A-3698C Reassigned to D. Prosch as Cognizant Engineer. l s i . A-2973 1984/85 outage ECN; now reassigned to M. Price. pA-4413 Now reassigned to V. leets 1 PLAN cc: P. Shortt SEEN S. Dutschke g6 ** 1 g D.C. Files-208 g E

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'b &w EN21NEERING ASSIGNMENT SHEET FOR ECN NO. M' 80% /4w A. Date: /O' 7-O' n Demy Basis Senorut Lmel Discipliner Enqpneer Report Resuired Review Engineer ( 3 ((B--O [. hr /T/E (53 Cognizant Engineer O Civil Engineer O ' diectric Design Engineer b.TAcSBc O N& C Design Engineer ((32b O l 1 O' Mechanical Design Engineer-M/d O e i t 1 O Nuclear Design Engineer O I8 ~ Licensing Engineer (50.59s) Bob Dieterich O I 1. The Manager of Ge1eration Engineering will assign / approve the Cognizant Engineer and will assign ~ the second Level Review Engineer (s), and will determine the need for a Design Basis Recor' (DRR) anti Generation Engine = ring review. 2. The Engineering & Quality Control Supervisor (Nucteer Operations) will determine the 50.59 status of the ECN. Those ECNs so identified will have a Safety Evaluation propered by the Licensing Engineer and a second level review i-in,.ir d by the assigned engineer. 3. The Cognizant Engineer is responsible for the completion of'all aspects of the design, but may request assistance, including help in preparing the DBR from the assigned design engineers. If the Cognizant Engineer feels he requires assistance from disciplines not checked on the ECN, he should contact the appropriate Supervising Engineer. j b-D. G. Raasch I Manager, G.r- -,o gggqe9M5RK HAS BEEN COMPLETED Ie ON AUG - 1985 'v i RANCHO SECO SITE DOCUMENT CCNTROL \\

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4ANCHO SECO WORK REQUEST PRESS FIRMLY, USING ON ALLPOINT PEN "'"'Y1TT INIT WO R K M EQU EST NO. O E PT. STATUS EQusPMENT l.0. .YuTvM 72036 GE bs 12 S -( FDS / A

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ECN No. A-3094, Rev. 1_ I ), hbMh of I sheet , e Pmpw.d By Hegn.u GA Cm ENGINEERING CHANGE NOTICE I' Jim Field 3/15/82 1 x i Auxiliar. ^+r System. MMott sc g Jim Field ( Ob 1/irju O THE FOLLOWING SYSTEM (S) WILL BE AFFECTED BY THIS CHANGE -~R ' vv nme n - l METEDiNN.R I l A R' P. Wichert L ~~'w I UAA/ < 0 A 76 ..n I 0 ~ ~ = / O REASON FOR CHANGE 104130 To improve the reliability of the Auxiliarv Foodwater i System per commitments made in the Distric'ts' December 17. 1979 letter to the NRC ~ (Mattimoe to Reid). To add " safety arade" flow instrumentation to the auxiliarv feadwater lines. O DESCRIPTION OF THIS CHANGE PROVIDE A D ETABLED DESCRIPTION AND ITS A PPECT ON PLANT OPER ATION. INCLUDE SM ETCH ES AND OTH ER PERTINE NT INFORM ATION TO COMPLETELY DESCRlEE AND ILLUSTR ATE HOW CH ANGE IS TO FUNCTION AS WELL AS d LLUSTR ATE INTEM-PACE (St WITH EXISTING E Q U I PM E NT. IM DBC ATE WHAT NEW C O M PO N E N T(S) ARE R E QUI R ED. D R AWINGS APPECTED AND ESTIM ATED M ATERI AL COSTS. Sub-ECN A: The Auxiliary-Feedwater- (AFW) Pump test line will be relocated. It will run"from the-AFW Crosstie line (between the crosstie valves) to the con-denser hotweIT._' A 3"' pneumatically activated control valve will be in-stal_ led-in-the-line. This-valve will fail closed whenever either of the - AFW-receives a " start" sTg~naCfr6iii EFICJConnection to EFIC will occur ~ i under-. a~ separate.1ECN. .._.._J~~ iA flowmeter (QA Class. 2)NilFbe ~added to the' test line to improve ~~ ~ ~ testabili ty.. - s Sub-ECN B: Safety-grade flow insWumentatio'nTorifice~ type) wiTT be added to the-- - ._ auxiliary feedwater line. These flowmeters will replace the interim ultrasonic meters currently in use. Drawings 'Affected:.. M-532[ Logic Diagrams Isometrics, Support M.aPiXNT WdWHAS Drawings, Raceway Drawings, I-Drawings BEEN COMPLETED Cost: Material - $200,0001 Labor _.- $20,000 - ON AU6 - 125 Engr. -- - $100,000 - ~ __~~'-- ~~ ~ ~ RANCHO SECO ~ ~ ~ SITE DOCUMENT CCNTROL rinsic.r. sr wno > f a CouMENp/n A-n . S n.s e h.,

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• 8 THE FOLLOWING SYSTEMtS) WILL BE AFFECTED BY THIS CHANGE E

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.=.. c-Improve reliability of the auxiliary feedwater system per comi'tmentrmade in the District's December 17, 1979 letter to the NRC staff (Mattimoe 'ta Reid) 8 DESCRIPTION OF THIS CHANGE (PROVIDE A DETABLED DESCRf PTION AND ITS A FFECT ON PLANT OPER ATION. INCLUDE SMETCHES AND OTHER PERTINENT 8

IN FO RM ATION FD COMPLETELY DESCRlBE AND ILLUSTR ATE HOW CH ANGE IS TO FUNCTION AS WELL AS ILLUSTR ATE INTER. FACE (S) WITH EXISTING E Q UIPM E NT. IMOICATE WH AT NEW CO M PO N E N T(S) ARE REQUIRED AND DR AWINGS AFFECTED. TOGETHER WITH ESTIM ATED M ATERI AL COST.] Please see attache'd. ~ ' ~ PLANT WORK HAS ? BEEN COMPLETED . c. ON AUG - 11985 (L --- RANCHO SECO ~ SITE DOCUMENT CONTROL j ^ 5 COMMENTS (indkate by whom) %n Lu all k1 H-S3 L ( (*a^f? ? DOb.Oon.OO % L 271Alu w dn A-2949 SUPERVi$ LNG ENQiNEER APPROVALS AS $NDICATED 8Y @ G T.epn i support G u n.nic.i 3 Ei.etrie.1 O cul G Nucl e @ Instrument.tlen O. h- '?/R A (j j h N 8.8 9/./ d i fu f PiJRTHER APP AOV ALS REQUIRED PryfNSUPf RVISING ENGINE E R O cn.no. oi oo ov o av: O i ues for A* ioa av soc: l'" '***'" '## a u.n

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(D Shmt 2 of 4 h n ECN A-2949 assumed the Auxiliary Feedwater System would be operated ~with the discharge cross connect isolation valves closed. From a system reliability aspect this no longer appears to be a sound choice because active failures, such as pump start failures, are more likely than passive failures, such as pipe ruptures. Therefore, ECN A-2949 has been cancelled and this ECN shifts back to the original commitment made in the District's December 17, 1979, Mattimoe to Reid letter. The configuration proposed in ~ this ECN will be stritable for operation with the discharge cross connect isolation valves either opened or closed. DESCRIPTION OF THIS CHANGE The current full flow test configuration for the Auxiliary Feedwater System requires that both auxiliary feedwater sides be disabled when testing the Auxiliary Feedwate: System on the "A" 0TSG side. This was recognized in the Auxiliary Feedwater System Reliability Study. As a result of that study, the District comitted in a December 17, 1979, Mattimoa to Reid letter to alter the full flow test configuration to improve reliability. A copy of the diagram from that commitment letter is attached. The intent in the comitment is to add a motor operated valve in the full flow test line. The valve should be operable from the control room. The final full flow test line may include other in-line devices. One such method is suggested below: This method will remove FWS-055, a globe valve used for throttling in the current test line, from its existing location. The "T" in .(11 the discharge line to the OTSG should probably be replaced with a short straight pipe section. This work will be in a Class 1 section of the system. FWS-055 will then be "T'd" into the discharge cross connect line. A motor operator may be added to FWS-055, or a motor operated valve may be added in series with FWS-055. The piping from the discharge cross connect through the motor operated isolation valve must be Class 1. Less than 10-feet of 6-inch Class 1 piping should be required. The full flow test line downstream of FWS-055 would be roughly 80 feet long if the test connection is routed to the condenser aat-well. Pipe whip considerations may dictate that the piping be beried. This burial project would be a significant portion of the project effort. An alternate route would be to direct the full flow test connection back to the condensate storage tank. In the existing configuration, FWS-055 is almost completely th during testing.Q,The pressure breakdown device might be install b in the line to allow greater range of action for FWS-055. U r An orifice or venturi should be included in the test line to allow flow measurement capability. It will eliminate the difficult method now used for measuring auxiliary feedwater flow. Flow is I now measured by timing drop in level of the condeng*:. n . ht.ETED M AS after the hot-well surge line to the condensate st) rag u oes E0cCNE CC TROW =

h 3}/. $0 , p been isolated. Local flow indication should be satisfactory because infrequent use of the full flow test line is anticipated, I I and because the operator must be at the pump to monitor suction and discharge pressures. P&ID M-532 is the only P&ID affected by this change. The cost of this project should not exceed $200,000. t 40PERSDED 1 M -}- ( PLANT WORK HAS BEEN COMPT.ETEO AUG - 1 E ON RANCHO SECO SITEDOCUMENT CONTROLj \\.

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IJAIE RECEIVED ECN # A-3094-A Sub ECN I i .,S DOC PREP DATE: ORIGINATOR: ~. V.. ISSUE DATE: 1-10-83 COG ENGINEER: J. Field NUCLEAR OPS ENGINEER: ROUTING INFORMATION DATE TO WHOM REASON DATE TO WHOM REASON DBR: Y E S [x] N0 []

50. 59 REQUIREMENT:

YES [xl LOG # 335 N0 [] ON HOLD DATE: REASON: ECN CONTENT: Improve reliability of Aux Feedwater System c.s W0kK REQUESTS: EM 71586 EM 71588/ GE 73033 / GE 74137 u GE 74138 / Gt %29to d Tc 3100 I ps m~gf / \\c 1162.1 / men 1?R40 t/ CLOSURE INFORMATION /-/9 f3mo bM w VA 6*DT**) DATE YELLOW MEN 0 SENT lt SCHEDULER: k sb'g' er E _y, _._.. 9..,; or.3. q v-- TO COG Ei1GR: _ 7-JLo-fd_m q_ M ) '2J-D COMMENTS: 1 ~... _.. _ _ DATE ECN CLOSED: ~~) -l.l-] O mo DATE PACKAGE SENT TO ECC: _7 - 0 8' O mO_

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I I '~ sheet pf ENGINEERING CHANGE NOTICE e. . av -.sn=t saa o.= K. Varma 8-23-82 1 O THE FOLLOWING SYSTEMtSi WILL BE AFFEC~ED BY THIS CHANGE J. Field Auxiliary Feedwater System R. P. Wichert u.tc t7 j wor. Oro.r No. NCR No. @ REASON FOR CHANGE yg TYPE ECN / To impro te the reliability of the Auxiliary Feedwater SINGULAR 0 6 4AJOR 01 5U5 W System per comments maae in the District's December 17. 1979 letter to .'MC-(Mattimoe to Reid) l O DESCRIPTION OF THl3 CHANGE

1. ROVIDE A DET ABLEO DESCRIPTION ANO ITS APPECT ON PLANT OPER ATION. INCLUDE SMETCNES AND OTNER PERTINENT I

IN FORM ATION TO COMPLETELY DESCRISE AND ILLUSTR ATE NOW CN ANGE IS TO PUNCTION AS WELL AS BLLUSTR ATE INTER. l P AC E(S) wlTM EXISTING E QUIPM E NT. IMOIC ATE WMAT NEW C O M PO N E NT(S) ARE REGUt REO, OR AwtNGS APPECTED AND E ST1M A T E D M ATERt AL COSTS. The Auxiliary Feedwater (AFW) pump test line will be relocated. It will run from the AFW crosstie.line (between the crosstie valves) to the condenser hotwell. A 3" pneumatically activated control valve will be i installed in the line. This valve will be fail-closed whenever either of the AFW receives a start signal from EFIC. Connection to EFIC will occur under ECii KSCG. ( flowmeter (CA Class 2) will be added to the test line to improve n testability. Drawings Affected: M-532, Isometrics, Support Drawings, Vendor Orawings. i Estimated Cost: 5250,000.00 gj[ bi . _,.0 WORK H AS BEEN COMPLETED / I ON JUL 211983 RANCHO SECO SITE CCCUMENT CONTROL 5 coMutNrS u au.re ey.aom, n / T // O I Jh Tg so a kV8 ** C*a -d_,l, w M.G.Eu,,.T. u.. ~~.43 5 V,

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tocFnso.ser Generation Engineering / Qesign i,asts Report Gr u.a.o.r. o.aw.tica GENERATION EhGINEERhG APPROVALS' Staff Acoroval (CBR) Eno AS INDICATED BY 2 !s. Required C is Required /' g'a** '*8af.y/..$ Is Not Required C Is Not Recuired C (. @n.a i CM.etrie.e f ~O civia O Nai." Agm % Y Lie ns1.n n,g aaf' 'ea a f,4 .O. e_+ ING/()f'? /_ W 'C$11$ TL ru ....,c m O cn.aS. o. .a Syctm comme==, cy Issueo For aors h er.comoi.e. M M M C wor.comoiet. A'd $$$ ,C 4 llU.u'du rio-V3 Q! '1lgo ga.....-.-,/.f.3 star..yo E,e4ne.r,na &a t.. i 7 r.......o.., .... i s;c a : te rewwrm

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l l " ~ ' SDC' 1 l ~ NO DRAWINGS OUT FOR REVISION. I NO NEW DRAWINGS SUsMITTED FOR PROCESSING i ._..f) rbfmum' 7-/Q-43 11 ' C o = SIGHATURE. DATE TIME U-"Cr

• • • • • • • • w*************w********************************w**********w**********.-

j ,,1. COGNIZANT ENGINEER ~ _ - 4:.-.,. .(NAME) .. J *.c (~,. EOLD PACKAGE. AT SDC AND AWAIT Yusu.a. DCN REVISIONS. b AND/OR ADDITIONS.TO BE. ISSUED 0N ".? INKS"- ~ EXPECT THEM WITHIN DAYS':. ADDITIONAL WORK REQUESTS MAY BE WRITTEN. 0R PLANT' WORK IS. COMPLETE AS DESCRI3ED IN EXISTING DCN TRANSMITTAL PKG(S,).. -.. AND THERE ARE NO OUTSTANDING NCR'S WHICH AFFECT THIS ECN SDC IS TO COMMENCE CLOSING OUT THE ECN, ISSUE PLANT WORK COMPLETE ~ ~' " YELLOWS" TO THE STICKS AND. PROCESS THE 50.59 IF APPLICABLE s. 6 i !H / llO 9 s.ar M.u. > ~ DATE/ / . ~.... S NATURE-,G. '. -u

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I P.EVIEi! 'e e?0M3E0 5G.59 FACILITY CHA'M Loc !b. I ~. C CESCP.IPTION: Inst.,i t e tanues anci ocu t.:e platus on t in.;s 31321-o"-oB2 and 3ta.23-,i -m... l Reloc. ire tha Au:::. lie:ry ceedwater ( AF'1) Pu:::o test i f n.c. Ec3 A-3622 will instalt ti.e ilm: trans:at:cce and controls. g i; NCR ECM d-30 79.6 g L I OESIGN BASIS REPORT REQUIRED: YesO "o D MUMBER OF PAGES (w/ attachments): SAFETY ANAL: SIS: SMETY ANALYSIS (w/ attachments): UGO. This change will provide safety grade indication of flow to each steam generator. The changes are quality and seismic Class I, udL de/av /N Ad*d r/M = Licens1no Engineer Cate Manacer Generation Encineerina Da 3 l PRC RECCMMENDATION: 50.59(a) Yes@ NoC 50.59(b) Yes@ NoO f__ e be v-DISPOSITION OF PRC.: her k . m e e_ l MSRC review prior to implementing C a. Unanimously recommends procosal @ e. b. Send to MSRC for concurrence f. Test of system required c. ModificationsRejected O g. 50.54(p) review recuired . %g, Iw ju-r, ( d. Return to Cognizant ' Engineer O .2 (,- PAC Chairman ae a. Recommend to Proceed Y Yes[C es C No L ANALYSIS: 50.59(a) ~ No b. Refer to MSRC 50.59(b) Yes c. Test of system required No d. Modificatd n rejected O k gg 7 g n Tm u m wrx.m eru) 6 ,_ JLi' 4 tv/H-l Plant Su:erintencent / One MSRC FINDINGS: 50.59(a) Yes No C 50.59(b) YesO NoO o (Ifapplicable) DISPOSITION OF MSRC: a. Recomenos prcposal O d. Return to Cogni: ant Engineer C e. Modification rejected C b. Send to NRC for aoproval C I c. Recomends not to_ proceed C MSRC Chairman

an-C0K4ISSION APPROVAL OBTAINED:

(If applicable) ':SRC Chair:an Nu ALL '..'ORK REQUESTS COF.PLETE A.10 YELLON 3. P.ETEST.COMPLiTE AND ACCEPTABLE: 'RAWINGS ISSUED (if applicable): (If aoplicable) \\.. Site Gocu-en: Controi One Snoervisor 6_ngr. A Quality Contret ? ?. UVERALL Mi'lli.:: Fiant mod 171Catton cnange complete. (If apolicable) . Manager Nuclear Opera:1ons M i-i. C0CL:ENTATIO:; CD:PLETE:

i Log 'lo. 3 15 l l ^ SAFETY. 2:!ALYSIS FOPMAT { . RANCHO SECO NUCLEAR GEilERATING STATI0tl UtlIT NO.1 ECil A-3094 Rev. 2 NCR Work Reouest t l DESCRIPTION: Install flanges and orifice plates on lines 31821-6"-DB2 and 31823-6"-DB2. Relocate the Auxiliary Feedwater (AFW) pump test line. ECN A-3622.will install the flow transmitter and controls. REASON FOR CHANGE: l To improve the reliability of the Auxiliary Feedwater system as committed in our December 17, 1979 submittal to the NRC and to implement the requirements of I mmEG 0737, ices II.E.1.2.2. EVALUATION AND BASIS FOR THE SAFETY FINDINGS: This change will provide safety grade indication of AFW flow to each steam generator. The changes are quality and seismic Class I. r. k.0 @ The proposed change will not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR or create the possibility for an accident or malfunction of a different type than any evaluated oreviously in the FSAR or reduce tne margin of safety as cefined in the basis for any Technic.*' Specification. SAFETY FINDI!!G: OThe procosed change does c.+e-involve a ch ge in the Technical Specifications v -- m w..a. R y i nau.s o m. ( 9!Ru Licensing Engineer [ [-s t_. Date // e Date /'//N/$L Review Engineer M // / / SM Uo.og t 3 9rso

.. ~ __ ~ s DESLUN n.\\ SIS REPORT (" s ECN ..-1094 NCR N/A Work Hequest _104]O E'b D' ' ~ Discipline ___ Mechanical Date 1-1. PURPOSE OF DESIGN CHANGE: The purpose of this desigIn change is to impleme'nt the requirements of NUREG 0737, item II.E.1.2.2, auxili..y flow indication. II. DESIGN CRITERIA USED: 1. Material to be Quality Class I.. compatible with existin~g boundary material. 2. Design configuration shall be analyzed to satisfactorily withstand a Seismic Category I event. l' 3. Flow resistance resulting franflow orifice installacion shall be 3 i analyzed to show no adverse effect on ability to supply auxiliary feedwater to the OTSG's at the required flow and pressure. 4. Piping will be installed to SMUD drawing M-870 and ASME Section XI, class 3. [; III. CALCULATIONS AND DESIGN INFORMATION: 1. Dead weight, thermal and seismic analysis'is acceptable (see attached). 2. The addition of* the flow orifice will result in 157.6 inches of H,0 pressure diff erential across the orifice at a flow rate of 1,000 gpm (see attached calculation). This converts to a 13.13' TDH/5.7 psi ~ loss across the orifice. E & W Doc. ID No. 15-1120580-02

Title:

System Description Auxiliary I Feedwater System requires a minimum flow of 780 gpm to one or both j OTSG at a OTSG pressure of.1050 psig. The (attached) AFW' system resistance curve indicates a line resistance of 75 ft. at 780 gpm. The flow orifice r'esistance at 780 gpm =tbiP2 " 'ds P d ) i dip 2 13 ' 13 (l'O0'0) 2S. P2

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q t Total real.stiin,ce = /5 6 7.93 = Wl.0 i t TDl! 9 780 :.:pm. (n. Th a mininaim av::llable

• Dil

'l 7EO ::pm is 2700 f t. TDil f rom P-313 (:4eu attached pump curves). 2700'~ - 83. 0 ' = 2617.0 ' TDit available for delivery. 2617.0' TDil = 1130.0 psig Therefore, the 'line can supply 780 gpm to the 0TSG at 1133 psig. This is greater than the minimum required. This calculation is conservative because the (attached) curve indicates that a flow ~ orifice with a S of 0.76029 will result in a 42% loss of,the actual differential. IV. FAILURE MODE: 'l. The configuration has been analyzed to withstand a Seismic Category I event. (See attached report). V. C0F0!ENTS : 1. Installation will be done 'in accordance with applicable approved procedures. 2. SP-210.01 A and B must reflect increased pressure drop. Design Enginee M'*D h, bL t Date 7 ou- /O ~N Review Engineer,- tt Date ) ,g{ ti.0. Designated f c.ngineer 1 Date 1 \\V

ENCLOSURE 5.11 ECN No. eS Transmittal Date r ( PACKAGE COVER SHEET To: SDC (M/S 265) To: 6 This Package Is Complete, Transmit To: Nuclear Operations Designated Engineer 6 The Major-0BR is complete, please attach copy to this package. 6 This Package Is Not Complete, Proceed with construction subject to conditions given in Attachment No. 2. 6 This Package Is Not Complete, Hold For: FROM: Cognizant Engineer () The complete ECN Package is submitted for your review and c ments. Please Mve world (, bema =iMwuse). review this p,L kage for the fo}l wing: Opc5 s c \\ Dfwe=1s MT bou frsv@n l M*LGION ($1Ee%IdGC. ( Agreement witgCFR50 59 gecipig A gb ## ,fa/ aYnainab tyL y # Mb G N '} * '!8 b - Training Requirements o( If comments are not received on or before (Date - Normally Five (5) working days), this package will be released by 50C for I construction. All comments are to be attached to this transmittal sheet and l returned to SDC. y Comments Attached bG M0+ 6 No Comments Nuclear Operations Designateo Engineer Date r Note: If "No Comments" is checked and signed by the Nuclear n-H nne i Designated Engineer, a signature by the Cosnizaggg@gg Not required. ."!'. : : 1::: Coments have been reviewed by the Cognizant Engineer and ECN pacWg g be released for construction. f}, 'g [ SITE COCWAENT CONT.R0tg V % r Oi!cahion l-)lIA Cb Date v' gnizant Engineer l __

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........N*. D5 E. Lawreese. Sr. ch. Lett. Ma rve t t en "a r s h.......................... 29 This ECN issued by $DC for deewestatica preparatton 3) ECN/DCM Ct.CS! (*17 C"EC%till only. os Mm). IS.19M w ludf.utO4 1. Att retlaw ocs - Pt'= =2d-f or stick files ORIGINAL LCN !!EL # AT SCC L!T!!L ALL CCC.'MT 4T10N 15 CowPLETE A;C ALL WOU GP7LZIE PCN TMMITTAL TACK. 2. All ECM and DC*t tranesntta! A*;t! c'.E SUN CMLETE3. sheet (s) septee run and seat tos 2 ' Tilt 3 COPY TOs ?.ALL M.0. Desta. Engr. STO' C.E. Cog. Engr. Originator s M v lN}NL 3 Originator .'.C)Va[ g Supv. Engr. C A 15.0. Designated East.

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RANCHO SECO SMUD Bcchtel Job 12334 MECHANICAL / PLANT DESIGN DESIGN CITY TO: FROM: J. l. /-l.. M E N90ZA /' / 2-b 3 SUBJECT OR TASK DATE: DESCRIPTION: 6vwuber db3 TASK NO. Fe eo w a p 9sss Li n-~ Tha following items are transmitted to you for your review, coninents and issue. If there are any questions or problems, please let us know. LIST OF DOCUMENTS NO. OTY DESCRIPTION M 532 3 SFIS O P & ID's M-188 3 SMTS Q Ortho Drawings M -19 8 i.S H T b Isometric Drawings \\[ g,. Q g S 5 31823f;DB 1 SH T Q Valve List 362H' DE2 3 SH75 318Z2-21i DE 3 SHT.S -O Line List 21922-0 D B l.5# T 32127-12-6B i SH T Q Bill of Materials 21691-60 D32 15nT C Pipe Support Drawings M-872 ,f*,f.~fg# bH,y'chh E n O Stress Report ON C Other JUL 211933 fsirec$puSIcg o SEco Q DBR CONTRop. O ECN C SAR t 'k This completes (partial) Mechanical / Plant Design Design City work responsibility for the above task. Additional Cements: ilP6 S'6'f'ft'2T DET M E WCAricC c<tu GE IWEb LATER (,. cc' w/anc3-w/o enc 1 e / K.' encl.

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RANCHO SECo N.P.S. Trcnsmittal Ni 126 MECHANICAL / PLANT DESIGN Bechtel Job N2 12334 T.kuau /d 14ea ( S k' s \\/ A R u A Faox: 2 8 3 SusJzCT on TASK DESCaIPTIoN: og TASK N8: 6 6.3 woD. Ni: 001 zCN N*: A-M4-A Tha following items are transmitted to you for your review, comments and issue. If there are any questions or problems, please let us know. LIST oF DOCUMENTS QTY DRAWING Ni COMMENTS 3 M-E32. g 3 13,, 3 M - 18 8 O ortbo Drawinss i, 4 3 / 9 2 7 6 f3 3 3 J $ 2 7.- 2 V2.- D 13 O Ic:matric Drawings i 31922.-6,,- 0 5 4 3 i % 2A -6"- o g p_ valva List 'g i 31691-6'i D82 ) 3 tl17 6 6 ,0 Linn List i 31 % 2 5 - 6"- D B 2 M - % 7 2. 7 319 2.4 -6 '- G B C Bill of Materials g g' g g O Pipa Support Drawings O other TotalN134 / ~ 7 Additional Comments: 55EN C t 'eEE T. N / ON JUL 211983 RANCHO SECO _ SITE CO 'UMENT CONTROL j g. y, ~ ec: w/ encl. cc: w/o encl. K. Walveker w/o encl. G. Deppe

1 .w. + .a c. --... :. a. t E /P N DESI@ Transmittal N1 2-Ei DESIGN CITY Bechtal Job NA 1233/. ("\\ kEu-VARMA raon: T k%4u / J..)AaA / MTE: 5 63 SUBJECT OR. TASK DESC1 M ION:

'ASK N8: $ 7 3 MOD. N8:

ECN N2: S-304M A V >< FE ED WATC/2. VP62bVE e "ho fc11owing items are transmitted to you for your review, commaants and issue. If there are my quascions or problems, please let us know. LIST OF DOCUMENTS QTT DRAWING Ni COMMENTS ] P & ID's ]. Ortho Drawings REVISED THLS DWf.1.5 TO EE M d7 4PPED g I,ommerte Drawings 4 31687-6 -6 6 FIEL.D W ELDS. ~.,"elve List i % Liha List i M g53 sl+T U 9 C 3411 of Macarials O Pipe Support Drawings 3 Other Total N1 6 I. b d Additional Comments: f AS T. KHAN / WO g{f"N 'COfMLETED ON JUL 211983 HANCHG SECO [ SITE Cec'UMENT CONTROLJ cc: v/ encl. cc: v/o encl. K. Walvekar v/o encl. G. Deuce

Q s RA'NCHO SECO WORK REQUEST PRESS FIRMLY, USING ONLY BALLPOINT PEN UN T -~ *i'itD E QU Es T NO. t ' T 586 &n.DkTU Hrn acsf Ms 9 k e / OEPT. sTA EQu EPM EN T 4.0 SYSTEM PHIQ HIT T I [ ')MIPM E N T N A M E \\ Yd a h frttc<e O t. 2 /,02 t/ em 4N 4 7 4 ATIO N DATE 4N4T6 ATION TIME EQU4P,NRs, p g to y E,30 2-3-22 o 7sr " ' ' = a g g P _ LEM,REouEsf o m.: . G c / u J o iv-;,, 9 o +. o d i a r a,. /, h- 'c l k ;,' 9 n i a / M a o + L, h;~ Esx H 7 x man SA n n A,en nJ2 < i,; t h ,.;a,:,. / A%. D,'<N 7"lE%~h4 Die. xw.2 y 6C gDCN NO. M N pOC N R EQ'O NPRD NCR QAC ss sE RI A LIZ E D NO, gg D R N d, = @-M 3 f YEs O NO @ vEs O NO M IN PECT. DAN R F ig PROC E DU R E(s) T EST R EQ'O YEs 0 NO T O Nod CN GIN EIRING REQUIREM ENTs ~ Y f! l - ~ / u..c / __/4 9 7'"'o /# / d 2: AP / v' e% ENGj N E E R l A.W!b s ,A_- n B an- / 'M r. ~"" ~.e ~, < / +g.,lwgJgrv[O/ /- = c ",= A Nr ~s V(gsu,eE a v isOR CLE A R ANCE / RwP a EsT o EsT o EsT o j ^ CO RDCCTIV E ACTIO N/ WOR K PE R FOR M ED ~ e ev ova aar tit A c e Fv m Pi p e.,, en no n s, os s aF F us s e s s~ n / W(, n WORK REQtES,i h,v. Oev x ntnOCn ~2 %$ - o 7 ' 2 y Lg,j a 6,. v Jv I I WORK HAS ._.4. C BEIN COMPLETED ~ -- " .y mm (f} f m ~~ ~ -- ON JUL 211983 g MANrWORFCO M g --SITE CdCUlWENT CONTROU,j I O TCT ccuePM ENT

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=~ O "53 ECN @ TRANS C ORAWING CHA.9GE TR AMS.*MT~AL NO. M -M 4 - A Sheet / of L PHEi%aED BY: g g, orca Sb?iRVIS;NG ENGINEER ES;GNED: S. Y20U D $ 10 k 2. 5 l C. I N wc.. r e ~ r c a s io, e.o 3, c a i .n ra ms 2 wr is m o r i._, DCN NUMBER IF NEVs ORAWING E 50.59 Log N. _ e-SY SOC /GEC WAITE "NEW" - y T P" E NCR No. OCN ORAWING i APERTURE ORAW:NG NUP.?SER NO. Ght. No. ! Rev. CA R O NO. + '2 WORK PERFORMED BY = B_ lE-/05" l 17 A \\,.si' l A Ba & !) 5 ' ""*"** ""*"* ~E ,/A i O l net < ) GENER AT!ON ENGINEERING - l g4 b E - adC m OTueR -- - ---C 4 4E - S a '1 5 !O ! Ned A' q g_A-1 E - 3 a3 ./5' I o I New A.o cemmu e/em<vs m W r 32816-342. I 2'7 l/4 ! AG A 895 6 ,, 'g _58lE-342. 157bl O ! Ne<J d ' ,, p / 'l E - 3 4 5-WEIOINed K' ~ W [f [ / q. _ /AJE g - /0 / 0

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h ECN @ TRANS G DRAWING CHANGE TRANSMITTAL NO. M 306 4 - M Sheet M of A PREPARED BY: J.. @ /2 A SUPERVISING ENGINEER 1 ASSIGNED: 3. t 2 ou.ros tol-) ?n J F~, e / c/ cocm. ANT, oE; ion e %,N e c a c4TE cmx a v.;r. s.v a r 'v o n t, DCM NUMBER IF NEW DRAWING E 50.59 Log No. BY SOC /GEC WRITE "N EW'- # E NCR No. DCN A ERWRE , E WORK PERFORMED BY DRAWING NUMBER N' sh:. No. l Ret. CARD NO. NUCt. EAR OPER ATIONS- - C l - f M Gd ) 17[ $ l 3 lM 4 - /,.,8 - O M ^ ^ $A 'n 3 Id2l7Zbf x 1 e, ) / s .n~A u 2 A A,.3i u s -," G,$ -; '#'? :! ' h - 0 ) Q3,"

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DATE RECElyED 5-27-82 ECN # A-3094-B Sub ECN DOC PREP DATE: ORIGINATOR: j- ~ ISSUE DATE: 1-10-83 COG ENGINEER: K. Varma NUCLEAR OPS ENGINEER: B. Wichert ROUTING INFORMATION DATE TO WHOM REASON DATE TO WHOM l REASON DBR: YES [d N0 []

50. 59 REQUIREMENT:

YES [C3 LOG # 335 N0 [] ON HOLD DATE: REASON: ECN CONTENT: Install flanges and orifice plates f_Q) -s WORK REQUESTS: GE 730VO / EM 2 &.30l CLOSURE INFORMATION M h R%% ofun cut 6-a r P7 og DATE YELLOW MENO SENT TO SCHEDULER: M w w 'C yde TO COG ENGR: M,#) 7 c/-fJ_a c, COMMENTS: DATE ECN CLOSED: b)l i3 M DATE PACEAGE 3ENT TO ECC: l_S k2'5 o C

N. O. UPDATE SHEET' s The attached ECN, A 3 o a /4 R~ l is wora com,1ete es ce this ante: NOTE: 6 DATE: U t/ d\\ )Q@3 .PER: ( / / Plant change (s) was authorized by the attached ECN and inp1emented through those DCN Transmittal Sheet (s). drcwing changes 11sted on the correlative Pursuant to the Rancho Seco Configuration Control Procedure, ECP-l', paragraph 4.7.2.l. you are to review those plant procedures for which you are responsible and initiate changes that are necessitated by this p1 ant modification. FLEASE l REVIEUER S IROUTE TO: TNTTTAT S ,0. CLUSB l SR' l R. COLOMBO 1 D. WHITNEY

G. COWARD

/ D. BLACIILY h R. MILLER C h _I 1. W. WELLS I J. WU ( K. McCARTIlY h [- //d3 COMMENTS: DATE SENT j [ / 9.8 3 BY ff" / / SDC Form 5-81 0)

a MAILING 5;.IP A:,t, A-30%,8, cu.i PROC 2551 % KEC W Ok: EON [j1 ?lIS COPY Tot w ;f. -$Titt FILt. !t - 7: Qj g., h L1hd h Mc ch.anict! Maint. ( Originator __ (t E/M Library N.O. Designated tngr. b Of) M 3!1ectri'El Sh P 1 4 C Shop p_ C.E. Cogniaant Engr. (T k1o b - Mh Cener.atton Engineering Supv. Engr. C y Admintatration / Supw. En$r. g y Training fG Contro1 Roo. "I

• Design City h,

Supv. Engr. M wi i J Q.C. Inspector Supv. Engr. N _32

• R. Dietetich. Licerising Engr 31 C. Coward, heleir Maint..

US R. t.awrence. Sr. Mech'. Engr... . 7 75 Marye11en Nrsh.. N This ECN is.ued by SDC for documentation preparation 3 EcN/DCN CLCSE ol'T CNECKLTST only. ON r/ k SY LC/n{l 1. All yellow DCN copias made for stick files ORICINAL ECN HELD AT 3DC WTIL ALL DOCO:ENTATION IS COPPI.ZTE AND ALL WOFX CC? FLETE DCN TKANSh1TTAL PACE-ACES HAVE BEEN COMPLETED. '2. All ECN and DCN transmittal sheet (s) copien run and sent to: N.O.Desig. Engr.[h I Mf8 2 THIS COPY TO: MAIL C.E. Cog. Engr.[ 6dQ @ Originator M Uh Originator M N #*M 31. g N.O. Designated Engr. W Supv. Engr. C C.E. Cognirart Eagr yyy , _,,e[ Supv. Engr. E ,..y J Supv. Engr. C R Supw. Engr. X 2. 8 m pfA Supv. Engr. E R Supv. Engr. N' M ("' CEC....... Supv. Engr. I E Supv. Engr. M b nh / ),2 copy for N.0. preceours up-() date.......... Supv. Engr. N J p,g,t,g, /

• Licensing Engr., R. Dieterich.

d 7 R . hinn.o n o Principal Proj. Engr.. J. McCalligan.. .no.m. 275 R. Ericho o. n..no p Supv. Nuclear Maint.. C. Coward. ~ %*hLeeM.sa6a.. J5Y-Plant Superintandent. P. Oubre. 200 Tech. Support. D. ilhitney........... Sc'heduling Office. S. Dutschke.... ~ J. McCo111gan......... aMO Start-up Engr..

8. Mc% hon.,...........

A ~ Supw. Special Agent. 8. Moore............ _J,8 Design City... e308 -7 Electrical ?".aint.. A. Locy.. 280 Site Res. Engr.. J. Jarkovich.......... ECC............ _.}6, Original ECN DC :*S and Transmittal

• • • ("

Plant Operations. D. 31ach17.......... R SMt;D Quality Ansurance. L. Schweiger.. J Above action completed: Accounting. J. Vance... J BY M* PRC Secretary. 215 ~ DATE 7" 8 /"8 8. Cen. Engr. Control. R. Warloe......... ]2, Site Drawing C.'ntrol. SDC.. 265 ] Paul Goode.in. Norwalk....... M. Ilum.nin. Desita City.. 20M ]2M I Connor Chin. CE............ ~ Desta Bird. Desten City... ( Matyvjlen Lrph. Lulen City. "9 Thim ECM inued by SDC for wi.rk to be tutt14ted i 3T L$l) / 4f.d UN f U (

• tt disposittooed 50.59

A-3C948 Rev.1 ECN No. re, 1 1 g.; ; Q Sheet-of ENG1NEERING CHANGE NOTICE Pa=$ 8v " ' S"" G ^ - G K. Varma 8-25-82 1 o Af S 1 O THE FOLLOWING SYSTEM (S) WILL CE AFFECTED BY THIS CHANGE J. Field C. ( 0 L'-- c

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Auxiliary teedwater system "'"'"*~'""*~'""""P~'""~ R. P. Wiche-_t fo-bb Worm Orcer No. NCR No. O REASON FOR OHANGE 104130 TYPE ECN i Lnange is required to meet tile requirements of SINGULAR U i MAJOR O ISUB Y, Mtu bulce 1.:;/ (to monitor operation) and Nt! REG 0737, 11 c.i.4.4.L (darety brace rion indictalon) O DESCRIPTION OF THIS CHANGE PROVIDE A DET ABLED DESCRIPTION A ND ITS A FFECT ON PLA NT OPE R ATIO N. INCLUDE SMETCHES AND OTHER PERTINENT IN FORM ATION To COMPLET'..Y DESCRISE AND ILLUSTR ATE HOW CH ANGE IS TO FUNCTION AS WELL AS ILLUSTR ATE INTER. F AC E{ S) WITH EXISTING E Q UIPIII E M r. IN DIC ATE WHAT NEW C O M PO N E NT($1 ARE REQUIRED, DR AWINGS APPECTED AND ESTIM ATED M ATERf AL COSTS. Install flances and orifice plates on lines 31821-6"-D82 and 31823-6"-082. Removal of interim ultrasonic meter and installation of flow transmitter and controls to occur under the major ECN A-3622. Drawings Affected: fi-162, "-168, Isometrics (. Estimated Cost: $40,000.00 (: f'LAhi v.w.u, a BEEN COMPLETED ON J(y 3, jeg RANCHO SECO SITE DOCUMENT CONTROL tw

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m a.,-O'-'OP'&w n e om.w ~w 5 t e ,e:- a L(Tm M ab._4 WJ ~ / ) k1 "~" JRTaoin me ud'Ity Co ' si porviso' to CFR So.597 Yes No O // sf-Fe n ve<. to. No. 73 T A. lo,!/d ( bm ' / [6 J,, ~ ..r. .m Generation Engineering / Design Basis Report g ueneger. oeneratio" GENERATION E8GINEER G APPRoVdLS Staff Approval (CBR) nom **'ino AS INDICATED BY I21 Is. Required, [ .Is Required 7 f / c4 jp/f/p Is Not Required O Is Not Recuired O / {L ns g gsiectrices O Civii O Nuclear O instrumentat'on gg a l ~~ 4 01.d2A 4/'/P a iofu /et 7, 11 o ne s oog. ones oavu .a i o ars on,e @ dhange Diseporwed sy: (Jee commereof ylssueo For morK MWork Comotete DsM @ Work Complete \\L!1 f ?Z l}"] SCC A Date Start-uo Engineerino Date a o ceu-a -,== ==== e..=__ <-=,u.- ......e, o.,. SMUD-o849 NOQ.'

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l 4 REVIEN OF PROPOSED 50.59 FACILITY CHA1GE Log.'!o. _3 j,.' DESCRIPTI0ti: Install f tanges and orifice plates on linea 3 t 32 t-o"--oB2 and 31323-6"-0a1. Relocate the Auxiliary Feedwater (AEW) Pump test line. ECN A-3622 will install the flowetransmitser and controls'. ~ ^ ECN A-3 0 7% O r/. L l4CR DESIGil BASIS ~ REPORT REQUIRED: Yes No NUMBER OF PAGES (w/ attachments): SAFETY ANALYSIS (w/ attachments):

AGE'i

. SAFETY ANALYSIS: 3: This; change:esill provide safety grade' indication of flow to each steam generator. The changes are quality and seismic Class I. h& dWF = g ra,M is/z9/w d Date Manaaer Generation Enoineerino Ca a Licensing Encineer I PRC RECOMMEllDATIDN:50.59(a) Yes@ NoO 50.59(b) YesS no O DISPOSITIDff 0F PliC: her Net b e Ne v-m o c. MSRC review prior to implementing C ' a. Unantmouslh recommends proposal @ e. b. Send to MSRC for concurrence Q f. Test of system required 3 c._ ModificationsRejected O g. 50.54(p) review recuired d:. Return to Cognizant' Engineer C g f p gj [ %e b Recommend to Proceed W M es. O No. PRC Chairman LYSIS: 50.59(a) Yes[./ a. No ' ~ b. Refer to MSRC M Test of system required O. lIO.N(b) Yes c. Irejected-0 kg f.7.gg n No O d. Modificat n W: NGAto AttrMo1M.3. C 5 /.L / V / C2:a Plant Suoerintencent ..MSRC FINDINGS: 50.59(a) Yes' No O 50.59(b) YesC NoO (Ifapplir.able) ' iIISPOSITIDN OF MSRC: a Recommends proposal O d. Return to Cognizant Engineer C e. Modification ' rejected C b:. Send to 'NRC for approval C c: Rarn=nands not to_ proceed ~01. uite MSRC Chairman i COMMISSION APPROVAL OBTAINED: (If applicable) Date MSRC Chatrman F ALL WORK. REQUESTS COMPLETE AND YELLOW 8. RETEST COMPLETE AND. ACCEPTABLE:

f. GRAWINGIISSUED (if applicable):

(If applicable)

1. Site-Occument Control Date Suaervisor Engr. & Quality Control R-t OVERALL REVIEW:

Plant mocification cnange complete. (Ef applicable) Manager Nuclear Goerations 2:e L 90C M MA H ON COMPLETE:

Log flo. 305 SAFETY ANALYSIS FOP.MT f', RANCHO SECO NUCLEAR GENERATING STATION UNIT NO.1 ECN -3094 Rev. 2 NCR Work Request DESCRIPTION: Install flanges and orifice plates on lines 31821-6"-DB2 and 31823-6"-DB2.

• Relocate the Auxiliary Feedwater (AFW) pump tdst line. ECN A-3622 will install the flow transmitter and controls.

REASON FOR CHANGE: To improve the reliability of the Auxiliary Feedwater system as committed in our December 17, 1979 submittal to the NRC and to *mplement the requirements of NUREG 0737, item II.E.1.2.2. EVALUATION AND BASIS FOR THE SAFETY FINDINGS: This change will provide. safety grade indication of A7W flow to each steam The changes are quality and seismic Class I. generator. (: e s @ The proposed change will not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR or create the. possibility for an accident or malfunction of a different type than any evaluated previously in the FSAR or reduce the margin of safety as defined in the basis for any Technical Specification. SAFETY FINDING: OThe proposed change does -net-involve a c,harge in the Technical Specifications -v; .a. Ry.e . q w m.c m. =r = - - - - //!z9!Rv Licensing Engineer [ 2v r__ Date Review Engineer, MN Oate /'/ C/$ b / /

DESIGN BASIS REPORT. C. ECN 'A-3094A NCR N/A Work Request f. Discipline Mechanical Date 8-25-82 I. PURPOSE OF DESIGN CHANGE: The purpose of this design change is ta implement the requirements of NUREG 0737, item II.E.1.2.2, auxiliary flow indication. II. DESIGN CRITERIA USED: 1. Material to be Quality Class I, compatible with existing boundary material. 2. Design configuration shall be analyzed to satisfactorily withstand a Seismic Category I event. 3. Flow resistance resulting for flow orifice installation shall be analyzed to show no adverse effect on ability to supply auxiliary feedwater to the OTSG's at the required flow and pressure. C:;'j Piping will be installed to SMUD drawing M-870 and ASME Section XI, 4. class 3. () III. CALCULATIONS AND DESIGN INFORMATION: 1. Dead weight, thermal and seismic analysis is acceptable (see attached). 2. The addition of the flow orifice will result in 157.6 inches of Ha0 pressure differential across the orifice at a flow rate of 1,000 gpm (see attached calculation). This converts to a 13.13' TDH/5.7 psi loss across the orifice. i I 8 & W Doc. ID No. 15-1120580-02

Title:

System Description Auxiliary Feedwater System requires a minimum flow of 760 gpm to one or both OTSG at a OTSG pressure of 1050 psig. The (attached) AFW system resistance curve indicates a line resistance of 75 ft. at 760 gpm. The flow orifice resistance at 760 gpm =2hP2 = iP.(f2)2 3 2hP2 = 13.13 (T') i 2hP2 = 7.58 ft TDH (_,

Total resistance = 75'~+ 7.58 = 82.6 ft TDH 9 760 gpm. The minimum available TDH 0 760 gpm is 2700 ft. TDH from P-318 (see attached pump curves). 2700' - 82.6' = 2617.4' TDH available for delivery. 2617.4' TDH = 1133.1 psig Therefve, the line can supply 760 gpm to the OTSG at 1133 psig. This is greater than the minimum required. This calculation is conservative because.the (attached) curve indicates that a flow . orifice with af of 0.76029 will result in a 42% loss of the actual differential. IV. FAILURE MODE: 1. The configuration has been analyzed to withstand a Seismic Category I event. (See attached report). V. COMMENTS: 1. Installation will be done in accordance with applicable approved procedures. Q O 8-s/w/m oesign Engineer oate b (, /0//o f FA Date Review Engineer / I y N.d Ochm4ec\\ DAtc E"$t h e er, f

ECN No'. W /d -# 82 - h Transmittal Date / PACKAGE CDVER SHEET To: SDC (M/S 265) To: LQThis Package Is Complete, Transmit To: Td. (>>$ M Nuclear Operations Designated Engineer L7 The Major-0BR is complete, please attach copy I to this package. l 1 L7 This Package Is Not Complete, Proceed with construction subject to conditions given in Attachment No. 2. ~ This Package Is Not Complete, H21d For: PLAN I' WVnn : a f g~ BEEN COMPLETED ON JUL 211.983 gggg. ( g Co ignT Engineer RANCHO SECO (D-The complete ECN Package is submitted for your review and w...E DOCUMENT CONTROL-- SIT U .... u. Pleita review this package for the following: Agreement with 10CFR50.59 Decisionb 7 C ManYan h sm hDCS N b'$ 1t nf5clO %Tf&e*h ' Ie es tu, If commen s are t received on or before (Date - Nonnally Five (5) working days), this package will ce releaseo by 50C for

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~ construction. All consnents are to be attached to this transmittal sheet and returned to SDC. DN getocNCg wt f#L./ /36By Comments Attached L/ No Comments Nuclear Operations Designateo Engineer Date Note: If "No Comments" is checked and signed by the Nuclear Operations Designated Engineer, a signature by the Cognizant Engineer is Not required. Cormnents have been reviewed by the Cognizant Engineer and ECN package will be released for construction. QL1 b'ir.J h j C gnizant Engmeer Date

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ECN No. A-3094B - h,M[ ; Sheet 1 of 1 f.. ENGINEERING CHANGE NOTICE Pr.oered By Mign.st GA Cl K. Varma 5/21/82 1 K. Varma i,_M h lp ? @ THE FOLLOWING SYSTEM (S) WILL BE AFFECTED BY THIS CHANGE _J.. Auxiliary Feedwater System r c* l R. P. Wichert /o. i f 2, l Worm oro.r No. NCR No. O REASON FOR CHANGE 104130 Change is required to meet the recuirements of REG Guido 1.47 (en mnniene nnavnein d and NUREG 0737. II E.1.2.2.C (Safety Grade Flow Indir neinni / n onnrnornrn i n,i( /m v' u GLFLAGLULU l eF "' ~ O OESCRIPTION OF THIS CHANGE () PROVIDE A DET At LED D ESCRIPTION A ND ITS AFFECT ON PLAN T OP ER ATIOPe. INCLUDE SKETCHES AND OTNER PERTINENT $N FORM ATION TO COMPLETELY DESCRISE AND ILLUSTR ATE HOW CN ANGE IS TO FUNCTION AS W ELL AS ILLUSTR ATE INTER. F AC E(S) WITN EXISTING E Q U I PM E N T. IND6C ATE WHAT NEW C O M PO N E NT(S) ARE R EQUI R E D. DR AWINGS AFFECTED AND ESTIM ATED M Af tf RI AL COSTS. Install flanges and orifice plates on lines 31821-6"-DB2 and 31823-6"-DB2. i Removal of interim ultrasonic meter and installation of flow transmitter and controls to occur under the major ECN A-3622. Floworificeplatesofp-1willbe_fabricatedforinstallationunderthisECN. h Drawings Affected: M-162, M-188, Isometrics Estimated Cost: S40,000.00 C? l T l PLAh g BEEN Co't&ET$ ON yp.:JIQ3 . ~N.T.ROL @ COMMENTS (indic.re by whomp Kn <9 4 6J 6, d w $., :m,,,s.x-d '>, : d F A l? 2 s l v i a n i , a e,, so,,,, y,, q 7 g 4. maan

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~ ~._ '\\ \\ O DESIGN BASIS REPORT s ECN A-3094-B NCR N/A Work Request 104130 Discipline Mechanical Date May 25, 1982 H A h i v.s,a., ..c I. PURPOSE OF DESIGN CHANCES BEEN COMPLETED j The purpose of this design change is to implement the .ehreMdateJ1%? l of NUREG 0737, Item II.E.1.2.2, auxiliary flow indicat Lon. RANCHO SECO II. DESIGN CRITERIA USED SITE DOCUMENT._CO_NTROL 1. Material to be Quality Class I, compatible with existing boundary. material. 2. Design configuration shall be analyzed to satisfactorily withstand a Seismic, Category I event. 3. Flow resistance resulting from flow orifice installation shall be analyzed to show no adverse affect on ability to supply auxiliary feedwater to the OTSG's at the required flow and pressure. 4. Piping will be installed to SMUD drawing M-870 and ASME Section XI, Class III. ? 1 5. The orifices to be installed under this ECN shall be of Beta ratio of 1.0. These will be replaced by the orifices of Beta ratio of 0.76029 s.t the time of connection to EFIC. III. CALCULATIONS AND DESIGN INFORMATION l l 1. Deadweight, Thermal and Seismic Analysis is acceptable (see attached). 2. The installation of the orifices of Beta ratio of 1.0 will not result j into an appreciable pressure differential across the orifice to l warrant the pressure differential calculation. IV. 3*AILUREMODE 1. The configuration has been analyzed to withstand a Seismic Category I event. (See attached report). V. COMMENTS 1. Installation will be done in accordance with applicable approved procedures. I DESIGN ENGINEER l^-- d - .[_ DATE I REVIEW ENGINEER DATE

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