ML18022A905

Rev 0 to Calculation SI-0044, Alternate Miniflow Orifice Strainer

ML18022A905
Person / Time
Site:	Harris
Issue date:	09/24/1992
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18010A852	List: ML18010A851 ML18010A853 ML18010A854 ML18010A855 ML18010A856 ML18010A864 ML18010A865 ML18022A904 ML18022A905 ML18022A906 ML18022A907
References
SI-0044, SI-0044-R00, SI-44, SI-44-R, NUDOCS 9210280204
Download: ML18022A905 (138)

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LIST OF EFFECTIVE PAGES Calc.

No. SZ-0044 Page No.

1 of 13 Revision 0

System File No.

2080 Page 1

2 3

4 5

6 7

8 9

10 11 12 13 Rev.

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0 TABLE OF CONTENTS List of Effective Pages Table of Contents PURPOSE LIST OF REFERENCES Page III'ODY OF CALCULATION 1.0 Assumptions and Bases 2.0 Strainer Basket Design Calculation 3.0 4.0 Strainer/Strainer Piping Friction Head Loss Impact of New Strainer/Strainer Piping on Recirc Line Friction Head Loss and Flow Rate IV.

CONCLUSIONS 13 V.

A.

ATTACHMEKZS Design Verification Record(s) and Design Review Check Sheet(s),

as appropriate 13

I.

PURPOSE Calc.

No. SX-0044 Page No.

2 of 13 Revision 0

System File No.

2080 The purpose-of this calculation is to provide analytical basis for the hydraulic design of the new SX pump altermate miniflow strainers to be installed by PCR-6547.

Specifically, this calculation provides the following:

hydraulic design inputs for the size and type of strainer basket; predicted friction head loss of the new strainer and strainer piping connection to the existing SX pump alternate miniflow piping, with the strainer both clean (i.e., unclogged) and clogged with the maximum ancitipated blockage material; and an analytical discussion of the friction head loss impact of the new strainer and strainer piping connection on the existing SX pump alternate miiflow piping, with the strainer both clean and clogged.

II.

LIST OF REFERENCES 1.

F.

M. White, "Fluid Mechanics",

McGraw-Hill Book Company, 1979 2.

M. R. Lindeburg, P.E.,

"Mechanical Engineering Review Manual'g Professional Publications, Inc., 7th Printing, 1984 3.

Crane Company Technical Paper f410, "Flow of Fluids Through Valves, Fittings, and Pipe",

22nd Printing, 1985 4.

Safety Injection System Design Basis Document No. DBD-f104 5.

CP&L Drawing No. SK-6547-M-2002, "SI/Charging Pumps Miniflow Recirc. Strainer",

Rev.

A 6.

CP&L Drawing No. SK-6547-M-2001, "Chem.

& Vol. Control Iso.

Revisions",

Rev.

A 7.

Shearon Harris Operations Surveillance Test, Procedure No.

OST-1007, "CVCS/SI System Operability Quarterly Interval Modes 1-2-3-4", Rev.

4, effective 2/13/90, test date 3/2/91 8.

Emdrac 1364-B070 "SHNPP Line List" XXI.

BODY OF CALCULATIONS 1.0 Assumptions.and Bases Water temperature is assumed to be 90 degrees F, which is the temperature at which the data in Ref.

7 is taken.

This is not the minimum SX flow temperature (i.e.,

40 degrees F).

However, the net change of the temperature effect on the friction head losses is insignificant in this range of SX flow temperature.

Additionally, the impact of the strainer on the total system SP will be the same regardless of the temperature.

Assumptions and Bases (cont'd)

Calc.

No. SI-0044 Page No.

3 of 13 Revision 0

System File No.

2080 The design flow rate of the SI pump alternate miniflow strainer is 60 gpm (Ref. 4).

The piping friction factor is defined using the Colebrook equation (Ref. 1, pg.

332, Equation 6.64).

The Colebrook equation is the analytical basis for the more commonly used Moody chart for friction factors versus Reynolds number.

Ref.

1 indicates a +/- 154 error on friction head loss calculations using the Colebrook equation.

Therefore, for conservatism, a 154 margin to allow for friction head loss error is added to the calculated friction head loss of the new strainer and strainer piping connection.

It is assumed that the total amount of debris which each strainer will capture is three pieces of 1/16"-thick, 8"p plastic.

7wis

~~s~v~< ve F m QEzicu >u~oies ~e ~~> Hawe'b~ c>>~~~

4.4

~~~vCC L-Kb For the purposes of this"calcuYation, The terms "clean" and "clogged" are defined as follows.

A "clean" strainer is 100% unclogged by debris, while a "clogged" strainer is one which has captured 100% of the anticipated blockage material.

For the purposes of this analysis, the difference between the pump discharge pressure of 2710 psig and the atmospheric pressure of the SI pump recirc flow inlet to the RWST is assumed to be the friction head loss of the recirc piping at the flow rate of 64 gpm (see Steps 3.3 and 4.2).

The elevation head change is considered insignificant.

The strainer entrance velocity head decrease is cancelled by the strainer exit velocity head increase;

hence, the net change is zero.

The elevation change between the pressure gauge and the RWST inlet would decrease the total SI pump alternate miniflow SP by about 63 feet.

The net effect on the total SI pump alternate miniflow SP would be approximately 1%:

(2710 2 '088) ft = 6256.8

((2710). 2.3088

63) ft = 6193.8 (6256.8 - 6193.8) 1.007 4

6256.8 ft 6P used in this analysis adjusted 6P It is conservatively assumed that the strainer basket is hydraulically modelled as a number of individual orifice plates.

The perforated section of the strainer basket contains 2688 1/8"p holes spaced 1/4" center-to-center.

The total surface area of the perforated section is (14.137" x 12.000"), or 169.646 sq. in., with 32.987 sq. in. of holes.

The basket is modelled as 2688 orifice plates measuring

.283" in diameter, with one.125" orifice per plate.

Each orifice plate is assumed to pass 1/2688th of the total flow through the strainer.

2.0 Strainer Basket Design Calculation Calc.

No.

SX-0044 Page No.

4 of 13 Revision 0

System File No.

2080 2.1 Assumption 1 '

identifies the maximum debris as three circular pieces of plastic 8" in diameter and 1/16" thick.

The surface area of the debris is:

2 (8 in)

A 3.

vr debris 4

Adebris 2

= 150.796. in 2.2 After collecting the debris, the strainer must allow the recirc flow to pass through an area at least as large as the recirc piping cross-sectional area.

From Refs.

8 and 3, the pipe ID and cross-sectional area are found:

XD

= 1.687 in pipe 2

A:= 2.241 in pipe 2.3 The minimum basket area is the sum of the areas in Steps 2.1 and 2.2.

After adding 5R for margin, the basket area is defined:

A fA

+ A.

I 1.05 basket

[ debris pipe J 2

BasketArea:=

161.0. in Abasket 2

= 160. 689. in 2.4 From Refs.

5 and 3, the strainer basket outside diameter is found.

Given the defined basket area, the outside diameter and circumference define the length.

Then the basket area is finalized:

BasketOD := 4.5 in BasketCircumf

= n'asketOD BasketArea BasketCircumf = 14.13'i in BasketLength BasketCircumf BasketLength

11.388 in BasketLength:

12 in BasketArea

= BasketLength BasketCircumf 2

BasketArea

= 169.646 in 2.5 From Refs.

5 and 3, the strainer housing diameter is found.

The clearance between the housing and the basket is defined:

HousingXD := 5.187 in Clearance HousingXD BasketOD Clearance

= 0.344 in

Calc.

No. SI-0044 Page No.

5 of 13 Revision 0

System File No. 2080 2.6 From Ref. 5, the basket hole size and spacing is defined.

From this, the number of holes in the basket is determined:

Hol~:=.125. in Columns:=

(12 in)

~

4 columns in rows Rows := (14 in) 4 in Columns = 48 columns TotalHoles := Columns Rows TotalHoles = 2688 holes Rows = 56 rows holes HcleeperSH?ncn

= 16 2

in 2.7 From the results of Steps 2.3 and 2.6, the surface area of metal and holes in the basket are determined:

Ahole 2

Hol~

Ahole 2

= 0.012272 in HoleArea := A TotalHoles hole MetalArea := BasketArea HoleArea 2

HoleArea = 32.987 i' MetalArea = 136.659 in 2.8 The hole area from Step 2.7 is the free-flow area of a clean basket.

The free-flow area of a basket clogged with the debris from Step 2.1 is required for the basis of the maximum strainer deltaP:

A

= A covered debris A

covered 2

= 150.796 in A

uncovered

= BasketArea - A covered A

uncovered 2

= 18.85 in 2.9 The number of uncovered holes is then determined.

It must be assumed that the maximum debris covers as many holes as possible:

CoveredHoles

= A

, HolesPerSqInch covered CoveredHoles

= 2412.7 holes CleanHoles

= TotalHoles CoveredHoles CleanHoles

= 275.3 holes

Calc.

No. SI-0044 Page No.

6 of 13 Revision 0

System File No. 2080 2.10 From Assumption 1.2, the design flow rate of the SI pump strainer is:

Q

= 60 gpm design 2.11 From Steps 2.6, 2.9, and 2.10, the minimum and maximum flow rates through the individual holes (depending on the degree to which the basket is fouled) is found:

HoleQ unclogged Qdesign TotalHoles HoleQ unclogged gpm

0. 022321 hole Qdesign gpm 0.217978 hole HoleQ unclogged HoleQ HoleQ clogged CleanHoles clogged 2.12 The flow velocity through the unclogged and clogged basket holes is then determined:

unclogged

,V clogged Ahole HoleQ clogged Ahole V

= 0.5836.

unclogged sec hole V

'= 5.6988.

clogged sec hole 3.0 Strainer/Strainer Piping Friction Head Loss 3.1 The friction head loss of each strainer and its piping connections to the existing recirc piping is the sum of the head losses of the components of the strainer/strainer piping connections.

Hl

= Hl

+ Hl

+ Hl

+Hl o

strainer piping

'ntrance basket exit Hl,piping

= Hl

+ Hl n

pipe fittings 3.2 From Assumption 1.1 and Ref. 2, the water density and kinematic viscosity at 90 degrees F are identified:

lb p := 62.11 3ft vkin 2

-5 0.826 10 sec

Calc.

No. SI-0044-Page No.

7 of 13 Revision 0

System File No.

2080 3.3 For the sake of comparison to actual test data, the friction head loss of the strainer and strainer piping connections are calculated at the same recirc flow rate as the flow test used for comparison (Ref. 7):

Q

= 64 gpm test 3.4 The deltaP for the piping is determined assuming clean commercial pipe.

From Ref. 2, assuming clean commercial steel pipe:

.0002 ft R

pipe ID pipe R

pipe 0.00142264 3.5 The flow velocity and Reynolds number for the piping is determined from the Q in Step 3.3:

Vel pipe Nrepipe Qtest A

pipe Vel ID pipe pipe vkin Vel pipe Nre pipe ft

= 9.163 sec

= 155945 3.6 From Assumption 1.3 and Ref.

1, the friction factor is determined:

j := 0..3

.015 0

f j+1 2'og R

pipe

+

2.51 0.015 0.02313 0.02282 0.02283 Fpiping

~ f 3

3 '

.5 Nre f

pipe

- j F

= 0.023 piping 3.7 From Refs.

5 and 6, the net change in the piping length is found.

The 2"f piping is reduced by the length of the strainer from the tip of the inlet connection to the centerline of the alternate miniflow nozzle:

Pipe length

= -21.5 in

Calc.

No. SI-0044 Page No.

8 of 13 Revision 0

System File No.

2080 3.8 From Refs.

6 and 3, the net change in fittings and their associated K values are identified.

The net change in fittings is zero, due to the fact that the strainer is to be installed in line with the existing piping, and no flow directions are changed:

Pipe length K

pipe

= Fpiping ID pipe K.

pipe

= -0.291 Kfittings

~

0 K

= K

+ K piping pipe fittings Kpiping

,0.291 3.9 From Ref. 2, the friction head loss of the piping is found:

Vel pipe Hl

=K piping piping 2

~ g BasketID := 4.26 in Hl'

-0.38 piping 3.10 From Refs.

5 and 3, the inside diameter of the basket is found:

3.11 The strainer entrance is modelled as a sudden enlargement.

Ref.

3 provides the method for determining the head loss of a sudden enlargement:

ID pipe Bincreaser BasketID Bincreaser

= 0.396 Kentrance 1-B increaser Kentrance 0.711 Hlentrance

= Kentrance Vel pipe 2'

Hl 'ntrance

= 0.928

Calc.

No. SI-0044 Page No.

9 of 13 Revision 0

System File No.

2080 The strainer basket is modelled as a number of 1/8"p orifices with each orifice passing its share of the flow.

The orifices are spaced 1/4" apart, center-to-center (Ref. 5).

The friction head loss is calculated for two bounding flow conditions:

a fully clogged strainer basket and a clean basket with no debris.

See Assumption 1.8 for a detailed discussion of the strainer basket modelling.

BasketArea hole BasketArea TotalHoles BasketArea hole 2

= 0. 063112 in Plat@

4 BasketArea hole Plate4

= 0.283 in Hol~ = 0.125 in gpm 0.02381.

hole HoleQ unclogged HoleQ unclogged TotalHoles The friction head loss is calculated for two bounding flow conditions:

a fully clogged strainer basket.

and a clean basket with no debris.

Qtest HoleQ clogged Qtest CleanHoles gpm HoleQ

= 0.23251 clogged hole The flow velocity through the unclogged and clogged basket holes is then determined:

V unclogged HoleQ unclogged Ahole V

0. 6225.

unclogged sec hole V

clogged HoleQ clogged Ahole V

6.0787 clogged sec hole

3.15 The Reynolds numbers are determined from 3.13:

V

. Hol~

unclogged Calc.

No. SI-0044 Page No.

10 of 13 Revision 0

System File No.

2080 the velocities in Step Nre unclogged vkin V

. Hol~

clogged Nre unclogged

= 785 Nre clogged vkin Nre

= 7666 clogged and friction head losses are

,C unclogged 8orifice

= 0.441 3.16 From Ref. 2, the basket K values determined:

Hol~

8orifice Plateful

.67 K

unclogged 1 - 8'rifice C

8 unclogged orifice C

.62 clogged K

= 47.463 unclogged K

clogged 1-8

~

orifice C

8 clogged orifice K

clogged

= 55.427 Hl unclogged

= K unclogged V

unclogged 2'g Hl

= 0.286 unclogged Hl clogged

= K clogged V

clogged 2'

Hl

= 31.828 "ft clogged

Calc.

No. SI-0044 Page No.

11 of 13 Revision 0

System File No.

2080 3.17 From Ref. 3, the strainer exit is modelled as a pipe reentrance:

K

=.5 exit Hl

=K exit exit Vel pipe 2'

Hlexit

= 0.652 3.18 From Step 3.1, the total strainer friction head loss is determined for the unclogged condition.

From Assumption 1.4, a 154 error is added to the head loss for conservatism:

Hl fHl

+ Hl

+ Hl unclogged L

piping entrance unclogged Hl

= 1.709 ft unclogged

+ Hl i 1.15 exit J dP unclogged

= Hl unclogged dP unclogged

= 0.737 psig From Step 3.1, the total strainer friction head loss is determined for the clogged condition.

From Assumption 1.4, a 154 error is added to the head loss for conservatism:

Hl clogged Hl

+ Hl

+ Hl piping entrance clogged

+ Hl

] 1.15 exit J Hl

= 37.982. ft clogged

= Hl

'P dP 16.383 psi clogged clogged clogged 4.0 Impact of New Strainer/Strainer Piping on Recirc Line Friction Head Loss and Flow Rate 4.1 The impact of the new SI pump recirc strainer and its associated piping connections must be addressed.

The head loss of the clean, unclogged strainer needs to be evaluated for mod acceptance testing purposes.

The head loss of the strainer after it has collected the full amount of debris needs to*be evaluated to ensure that the maximum friction head loss attributable to the strainer willstill allow the minimum required SI pump recirc flow to pass.

4.2 Ref.

7 is a record of the actual test data taken during a recirc flow test of SI Pump 1B-SB.

During this test, SI Pump 1B-SB was operated on recirc only, and a recirc flow of 64 gpm was observed.

The total differential pressure observed for the recirc line was 2710 pslg dPtotal 2710 psig

Calc.

No. SI-0044 Page No.

12 of 13 Revision 0

System File No.

2080 4.3 From Step 3.18, the total pressure drop of the unclogged strainer is:

dP

= 0.737 ps1g unclogged 4.4 Adding the unclogged strainer pressure drop to the total differential pressure of the recirc line will not change the total pressure drop of the recirc line.

A new equilibrium recirc flow rate would result.

Since the change in Q is proportional to the square root of the change in pressure drop:

dP

~

dP recirc total dP unclogged dPrecirc 2709.263 psig NewQ unclogged

~

Qtest dPrecirc dPtotal NewQ

= 63.991 gpm unclogged Qtest NewQ unclogged Qtest 0.014 4.5 From Step 3.19, the total pressure drop of the clogged strainer is:

dP

= 16.383 psig clogged 4.6 Adding the clogged strainer pressure drop to the total differential pressure of the recirc line will not change the total pressure drop of the recirc line.

A new equilibrium recirc flow rate would result.

Since the change in Q is proportional to the square root of the change in pressure drop:

dP

~

dp

• -dP recirc total clogged dPrecirc

= 2693.617 psig NewQ clogged o

Qtest dPrecirc dPtotal NewQ

= 63.806 gpm clogged Qtest NewQ clogged Qtest 0.303 4

, Calc.

No. SI-0044 Page No.

13 of 13 Revision 0

System File No.

2080 IV.

CONCLUSIONS From Sections 3.0 and 4.0 of this calculation, it can be concluded that the anticipated friction pressure drop of the new SI pump strainer and its associated piping connections will have an insignificant effect on the total differential pressure experienced by the SI pump alternate miniflow line.

Even when the strainer is clogged with the maximum anticipated debris, the reduction in total SI pump alternate miniflow flow is less than 14 (see Step 4.6 above).

As stated in Assumption 1.4, a 154 add-on for friction head loss calculation error is appropriate for this calculation. It should be noted that the impact on the total SI pump alternate miniflow would be even less if the 15% error is not included.

In conclusion, the SI pump recirc strainer will have an insignificant effect on SI pump alternate miniflow, whether it is clogged or unclogged, and with or without the 15~ error added to the head loss calculation.

V.

ATTACHMENTS A.

Design Verification Record(s) and Design Review Check Sheet(s),

as appropriate

DISCIPLINE DESIGN VERZPICATION RECORD ltmtrLs:ti~ to Verification Persornel Page 1

Plant Pro ject F i le Ho.

Document Ho.

S Rev CI Level

[~Q, (Class A)

[ ) Seismic (Class g)

[ )

FP-Q (Class 0)

[ ) Other Design verification should be done in accordance vith AHSi H45.2.11, Section 6, as an>>noed by Regulatory Cuide 1.64, Rev. 2.

Special instructions:

Discipline Project Engineer il.

Verification D~tation Applicability Disci line Hechani ca l HVAC Electrical

>ac Other

[][)

[.)

Disci line C ivil Structural Seismic Equip. Qual.

Civil Stress Fire Protection Envirom>>ntal Qualification Huaan Factors Haterials

[)[)[)[)[)[)[)[)[)

Ver)fioat'ion Hethods Used:

M Design Revie~

[ ] Alternate Calculations

" [') Qualification Testing Design Docuaent Acceptahlr:

Tr' Ho [ ) - cannents attached.

~j Design Verifier Da'te Acksxwledgement of Vr~H'icationt (OPE) c

~

pp /i/2 Date l]I. Resolutim of'C~st Comnents Resolved (See Attached):

(RE)

Action taken s>>kes Design Documents Acceptable:

Design Verifier Date Oa'te (DPE)

Date HED procedure 3.3/Rev.

5D

Page 1

DES EGN REVIEW CHECK SHEET Plant Document Type

~Lc.

Project File No.

Document No.

Revision

==

Description:==

.Mark each item yes, no, or not applicable and initial each item checked by you.

1.

Were the inputs correctly selected and incorporated into design?

2.

Are assumptions used in the design adequately described and reasonable?

NOTE: Reviev shall include but is not limited to applicable inputs specified in NED Procedure 3.1.h, paragraph 3.1.A.4.

3.

Are the appropriate quality and quality assurance requirements specified?

4.

Are applicable

codes, standards, and regulatory requirements including issue and addendum properly identified, and are their requirements for design met?

5.

Has applicable construction and operating experience been considered?

6.

Have design interface requirements been satisfied?

7.

Was an appropriate design method used?

8.

Ts the output reasonable compared to inputs?

9.

Are the specified parts, equipment, and processes suitable for the application?

10. Are the specified materials compatible ~ith each other and the design environmental conditions to which the materials vill be exposed?

+Gv.

o Page 2

Document Type Document No.

Revision 11.

Have adequate maintenance features and requirements been specified?

sv-n f9 12.

Are accessibility and other provisions adequate for performance of mai.ntenance,

repair, and any expected in-service inspections?

13.

Has the design properly considered radiation exposure to the public and to plant personnel (ALMA.)?

14. Are acceptance criteria in the design documents sufficient to allow verification that design requirements have been satisfactorily accomplished?

15.

Have adequate preoperational and periodic been specified?

~

~

16.

Are adequate storing, handling,

cleaning, requirements specified?

test requirements

shipping, and identification

~al >

17.

Are requirements for record preparation, revie~, approval, retention, etc., adequately specified?

18.

Have all problems with this design 3cnown from prior application been considered and resolved?

~/I For each question on the chec3c list not answered yes, explain below.

If "Not Applicable give reason.

S'ignature (Design Verifier)

Date II. Phi- +p>'~big g K ~

Cgc<>id (g.

ilaw Qfl JW lo

~~

> C

SYSTEM/

CALC. TYPE 2005 DD CAROLINA POWER

& LIGHT COMPANY HNP-I INST-1044 (CALCULATION g)

FOR Reactor Coolant Wide Ran e Pressure:

CSIP Alternate Mini-Flow Interlock Accurac Calculation Loo s P-402

& P-403 (TITLE INCLUDING STRUCTURE/SYSTEM/COMPONENT)

FOR SHEARON HARRIS TECH SPECS AND SETPOINTS HESS I&C (PROJECT AND/OR PLANT NAME & APPLICABLE UNIT)

YES SAFETY RELATED:

5 No0 SEISMIC APPROVAL REV.

NO.

PREPARED BY DATE VERIFIED BY DATE PROJ.

ENGINEER DATE PRIN.

ENGINEER DATE P >IIPZ 2/

Z.

9 ~~/rz REASON FOR CHANGE:

REASON FOR CHANGE:

REASON FOR CHANGE:

List of Effective Pages Page No. i Calculation No, HNP-I/INST-1044 Rev.

0 PAGE 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 REV PAGE 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 REV PAGE REV ATTACHMENTS

Table'of Contents Page No. ii Calculation No. HNP-I/INST-1044 Rev.

0 Pacae No.

1.0 OBJECTIVE o

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o 1

2.0 LOOP FUNCTIONALDESCRIPTION................

1

3.0 REFERENCES

1 4.0 INPUTS AND ASSUMPTIONS....................

5 5.0 DETERMINATIONOF UNCERTAINTIES.............

7 7 o0 FIGURES o

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~

~

15

Pnmputed b~.

Chocke~'AR/PZD No.:

Date:

Date:

CAROLINA POWER Si LIGHT COMPJLNY CALCULATION SHEET Calculation ID:

HNP-I/INST-1044 Pg.

1 Rev.

0 File:

Project

Title:

Shearon Harris Setpoints Calculation

Title:

RCS Wide Range Pressure:

Accuracy and Setpoint Calculation Status:

Prelim.

Q Final ~

Void Q 1+0 OBJECTIVE The objective of this calculation is to determine the inaccuracies associated with the.RCS Wide Range Pressure Bistable for the CSZP Alternate Mini-Flow Interlock channels.

This calculation is being prepared to comply with CPGL commitments to Reg.

Guide 1.105 as outlined in FSAR Section 1.8.

In addition, this calculation has been prepared to be consistent with the methodology outlined in ISA S.67-04.

2 '

LOOP FUNCTIONAL DESCRIPTION 2.1 Instrumentation is provided to monitor the RCS Wide Range Pressure.

Bistables provide an interlock to open and close the motor operated valves on the CSZP Alternate Mini-Flow line.

3 ~ 0 REFERENCES

3. 1 SHNPP Drawings 3 ~ 1 ~ 1 CAR-2165-G-844 R4 "RCS RVLIS Flow Diagram".

3.1.2 CAR-2166-B-401 Sh.197 R8 "RCS Pressure Znstrumentation-CWD".

3.1.3 CAR-2166-B-401 Sh.317 R5 "CVCS MiniFlow Valve 2CS-V757SA CWD".

3'.4 CAR-2166-B-401 Sh.319 R5 "CVCS MiniFlow Valve 2CS-V757SB-1 CWD" ~

3 ~ 1.5 CAR-2166-B-431 Sh.L-74 R6 "RVLZS Instrument Installation Detail" 3'.6 3.1 ~ 7 3 ~ 1 ~ 8 3'.9 3ol ~ 10 3 '.11

3. 1. 12 CAR-2166-B-431 Sh.L-75 R5 "RVLZS Instrument Installation Detail" CAR-2166-B-431 Sh.L-78 R2 "RVLIS Instrument Installation Detail" CAR-2166-B-432 RSO "Instrument Index" CAR-2166-G-436 Sh. 2 R10 "Reactor Aux. Building El. 236

'nstrument Arrangement".

CAR-2166-G-437 Sh.3 Rll "Reactor Aux. Building E1.236'nstrument Arrangement".

CAR-2166-S-PRC0402 Rl "RCS Wide Range Pressure Loop 3 Loop Diagram".

CAR-2166-S-PRC0402/1 RO "RCS Wide Range Press'ure Loop 3 Loop Diagram".

~her I or4 TAR/PID No.:

Date:

Date:

CAROLINA POWER 4 LIGHT COMPANY CALCULATION SHEET Calculation ZD:

HNP-I/INST-1044 Pg.

2 Rev.

0 File:

Project

Title:

Shearon Harris Setpoints Calculation

Title:

RCS Wide Range Pressure:

Accuracy and Setpoint Calculation Status:

Prelim.

Q Final g Void Q

3. 1. 13 3

~ 1 ~ 14 3 ' '5 3.1.16 3 '.17 3 ' '8 CAR-2166-S-PRC0403 Rl "RCS Wide Range Pressure Loop 1 Loop Diagram".

CAR-2166-S-2500 R7 EQDP "Section 8.0 Sensors".

CAR-2166-S-9000 R3 "Post Accident Monitoring Equipment, Regulation Guide 1.97".

Emdracs 1364-1328 Sh.29 R15 "Process Control Block Diagram".

Emdracs 1364-46574 Sh.22 R8 "RCS Wide Range Pressure P-402 ZWD".

Emdracs 1364-46577 Sh.8 R6 "RCS Wide Range Pressure P-403 ZWD" ~

3 '

~ 19 Emdracs 1364-92079 Sh.ll R5 "RCS Wide Range Pressure P-402 ZWD".

3.1.20 3 ' '1 3 ~ 1 ~ 22 3.1 ~ 23 3 '.24 Emdracs 1364-47254 R4 "RVLZS Transmitters Group A".

Emdracs 1364-52638 R2 "RVLZS Transmitters Group B".

Emdracs 1364-52497 R3 "RCS Flow Diagram".

Emdracs 1364-B-0070 R45 "Line As-Built Master List".

CAR-2166-B-431 Sh.LP-01 R6 "Typical Pressurizer Instrument Installation Detail" 3 ~ 1 ~ 25 3.1.26 Emdracs 1364-92079 Sh.9 R4 "Pressurizer Pressure P-455 ZWD" ~

Emdracs 1364-46574 Sh.20 R8 "Pressurizer Pressure P-455 IWD".

3 '.27 Emdracs 1364-46575 Sh.19 R7 "Pressurizer Pressure P-456 ZWD".

3 ~ 1 ~ 28 Emdracs 1364-46576 Sh.15 R7 "Pressurizer Pressure P-457 IWD".

3.2 SHNPP Updated FSAR 3.2. 1 3

F 2 3 ~ 2 ~ 3 Section 1.8 "Conformance to USNRC Reg Guide 1.105".

Section 9.4.0 R27 "Air Conditioning, Heating, Cooling,

and, Ventilation System".

Figure 3.11B-4 R40 "Reactor Aux. Building E1.236'nvironmental Parameters During Normal 6 Post Accident Environments".

gmruot csR TAR/PZD No.:

Date:

Date:

CAROLINA POWER

& LIGHT COMPANY CALCULATION SHEET Calculation ZD:

HNP-I/INST-1044 Pg.

3 Rev.

0 File:

Project

Title:

• Shearon Harris Setpoints Calculation

Title:

RCS Wide Range Pressure:

Accuracy and Setpoint Calculation Status:

Prelim.

Q Final g Void Q 3.2.4 Figure 3.11B-12 R42 "Reactor Aux. Building E1.305'nvironmental Parameters During Normal

& Post Accident Environments".

.3 ' '

Figure 3.11B-23 R40 "Reactor Aux. Building E1.236'ntegrated Radiation Doses To Equip. During Normal

& Post-Accident Environments".

3.2.6 Figure 3.11B>>26 R42 "Reactor Aux. Building El.305'ntegrated Radiation Doses To Equip. During Normal

& Post-Accident Environments".

3.3 SHNPP System Descriptions and Technical Specifications 3.3.1 3 ~ 3 ~ 2 SD-100.01 R2 "Reactor Coolant System".

SD-107 R2 "Chemical and Volume Control System".

3.4 CP&L Design Guides 3'.1 DG-VZZZ.50 R2 "Instrument Setpoints".

3.5 Vendor Literature 3.5

~ 1 3.5 ~ 2 3 ~ 5.3 3 ~ 5 ~ 4 3+5

~ 5 3~5.6 3.5.7 3.5.8 VM-ONY "ZTT Barton Technical Manual" or VM-BFL "Tobar Technical Manual" and including latest vendor literature.

VM-OSE "Westinghouse RVLIS Manual".

VM-PYC/PNO "Westinghouse Analog Controls".

Westinghouse WCAP-8687 Supp.2-E13 Rev.2 "Equipment Qualification Test Report Process Protection System".

"Westinghouse Setpoint Methodology for Protection Systems Shearon Harris, Rev. 1" VM-ZSP-V02 "Charging Safety Injection Pumps".

Westinghouse CQL-TAC-01 S.O.

280 "High Head Safety Injection System".

Westinghouse Letter 92CP*-G-0096 From Pamela M. Stevenson To Tomas M. Dresser September 3,

1992 "Proposed'ew TAC for High Head Safety Injection".

e

Cog,.~e it-ad

@ger 1

4a.

~

TAR/PID No.:

Date:

Date:

CAROLINA POWER 5 LIGHT COMPANY CALCULATION SHEET Calculation ID:

HNP-I/INST-1044 Pg.

4 Rev.

0 File:

Project

Title:

Shearon Harris Setpoints Calculation

Title:

RCS Wide Range Pressure:

Accuracy and Setpoint Calculation Status:

Prelim.

Q Final g Void P 3.6 SHNPP Procedures and Scaling Documents 3.6.1 MST-Z0080 R2 "RCS Wide Range Pressure P-402 Calibration".

3 ~ 6 ~ 2 3.6.3 3.6.4 MST-Z0081 R2 "RCS Wide Range Pressure P-403 Calibration".

SCN-061 R3 "RCS Wide Range Pressure Loop 1 P-403".

SCN-062 R4 "RCS Wide Range Pressure Loop 3 P-402".

C 3.7 Industry Standards and Reference 3 ~ 7.1 ZSA Standard S67.04 "Setpoints For Nuclear Safety Related Instrumentation Used Zn Nuclear Power Plants".

3 ~ 7.2 ZSA Standard dRP67.04 "Methodologies For The Determination Of Setpoints For Nuclear Safety Related Instrumentation",

Draft 9.

3 ~ 7 ~ 3 3.7.4 USNRC Reg.

Guide 1.105 "Instrument Setpoints For Safety Related Systems".

ASME R5 "Steam Tables".

3.8 Other References 3 ~ 8 ~ 1 3 ~ 8 ~ 2 Equipment Data Base System (EDBS)

PCR-5322 "Replacement of Reactor Vessel Level Instrumentation".

3,8.3 3'.4 PCR-6547 "CSIP Alternate Mini-Flow".

Calculation HNP-I/INST-1003 RO "Pressurizer Pressure Error Analysis".

TAR/PID No.:

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CAROLZNA POWER

& LIGHT COMPANY CALCULATION SHEET Calculation ID:

HNP-I/INST-1044 Pg.

5 Rev.

0 File:

Project

Title:

Shearon Harris Setpoints Calculation

Title:

RCS Wide Range Pressure:

Accuracy and Setpoint Calculation Status:

Prelim.

Final ~

Void Q

4. 0 INPUTS AND ASSUMPTIONS F 1 Based on a review of the references, there are no known dependent uncertainties for any of the components in this calculation.

Calibration tolerances will be considered as biased uncertainties, since they occur in a known direction and are not considered random.

4 '

All final values of this calculation will be rounded to two decimal places to achieve a consistent calculation format.

4 ~ 3 Any uncertainty determined to be lese than or equal to 1/10 the magnitude of the greatest uncertainty will be considered insignificant and may be left out of this calculation.

4.4 This calculation refers to a loop as a group of one or more related instrument channels.

A channel is referred to as the path in the loop that goes from the process being measured to the bistable used for valve interlock.

4 '

The pressure transmitters and hydraulic isolators are located on the El.236'evel of the Reactor Auxiliary Building.

This is an inside area which is exposed to temperature extremes of 60'F to 104'F during normal operation.

Only Train A has an accident temperature of up to 120'F

[Ref. 3.2.2, 3.2.3].

For the purpose of this calculation, it is assumed that calibration could occur anywhere within the above stated normal temperature ranges of the instruments and processes.

4 '

4.7 The control room is designed to maintain a temperature between 72'F and 75 F for all operating conditions

[Ref 3.2.2).

The PIC room is designed to maintain a temperature between 65'F and 80'F for all operating conditions

[Ref. 3.2.2).

The uncertainties associated with radiation in the control and PIC room and the uncertainties associated with temperature in the control room are considered negligible per Ref.

3 ' 'g 3 '

6J 3 ' 'g 3 '

5t'nd Assumption 4 ' 'he seismic effects on Westinghouse 7300 series cards in the PZC room are considered negligible per Ref. 3.5.5.

The RCS Wide Range Pressure and associated equipment and controls are classified as nuclear safety related.

For the purpose of this calculation, both normal and accident environmental conditions will be used to calculate instrument uncertainties.

4.8 4.9 The RCS Wide Range pressure transmitters are ZTT Barton Model 763 (Rated Span

~ 3000 psig) and Tobar Model 32PA2 (URL ~ 6000 psig)

[Ref.

3.6,3.1.20, 3.1.21) with a calibrated span of 3000 psig.

The output of the transmitters produce a 4-20ma signal that is proportional to the input pressure

[Ref. 3.5.1, 3.8.2).

Uncertainty values given in Upper Range Limit (Tobar) will be converted to calibrated span by applying a factor of a turndown ratio (URL/Cal.

Span) or (6000/3000),

which gives a value of 2.00 [Ref. 3.5.1).

rnmauted '-

Chp>>~ad ~- ~

TAhga ID No.:

Date:

Date:

CAROLINA POWER fc LIGHT COMPANY CALCULATION SHEET Calculation ID:

HNP-I/INST-1044 Pg.

6 Rev.

0 File:

Project

Title:

Shearon Harris Setpoints Calculation

Title:

RCS Wide Range Pressure:

Accuracy and Setpoint Calculation Status:

Prelim.

Q Final g Void Q

4. 10 For the calibration of instruments, the following Measurement and Test Equipment (M&TE) inaccuracies will be dragon upon.

The pressure gauge used during calibration has a required accuracy of +15 psig [Ref. 3.6].

Converting this to percent span is as follows:

MTEPG = k[(15/3000)

~ 100%]

Span MTEPG = +0.50%

Span The digital multimeter used during calibration has a required accuracy of +0.02 vdc [Ref. 3.6, 3.8.3].

~ Converting this to percent span is as follows:

MTE~ = k[(0.02v)/(5v-lv) ~ 100%]

MTE~ = R0.50't Span F 11 4 ~ 12 The expected maximum 40 year normal operation Total Integrated Dose (TID) in the location of the subject transmitters is 4030 Rads and the expected maximum one month TID during an accident is 370000 Rads

[Ref.

3.2.5].

The error due to normal radiation effects is calibrated out every 18 (24 conservatively) months.

Therefore, the maximum normal radiation exposure between calibration is considered to be:

RENO~

(4030 Rads / 40)

~

2 201.5 Rads TZD The ZTT Barton Model 763 transmitter uncertainties will be used to calculate the final results since they are the more conservative of the transmitter uncertainties.

4 ~ 13 The minimum required flow through the CSZP is 60 gpm [Ref. 3.5.6].

HESS/Mechanical has addressed the problem of measuring RCS pressure to insure a low enough CSZP discharge pressure so that the minimum required flow is guaranteed.

The maximum allowed RCS pressure without alternate miniflow to protect the CSZp's is 2419 psig.

See Figure 7.4 for memo.

The elevation of the RCS hot leg is assumed to be at 252'-6.5"

[Ref.

3.6].

The elevation of the pressurirer level lower tap is 266'-4.75"

[Ref. 3.1.24].

~,4 qy>>

I TAR/PID No.:

Date:

Date:

CAROLINA POWER Sc LIGHT COMPANY

,'ALCULATION SHEET Calculation ID:

HNP-I/INST-1044 Pg.

7 Rev.

0 File:

Project

Title:

Shearon Harris Setpointo Calculation

Title:

RCS Wide Range Pressure:

Accuracy and Setpoint Calculation Status:

Final g Void Q 5 '

DETERMINATION OF UNCERTAINTIES 5.1 Process Effects 5 ~ 1 ~ 1 5 ~ 1 ~ 2 Head Correction - The errors due to head correction are insignificant compared to the high pressures being measured

[Ref. 3.6, Assumption 4.3).

Sensor Bellows Sensin Lines H draulic Isolator - The errors due to resistive forces, temperature, and other miscellaneous items are insignificant compared to the high pressures being measured

[Ref. 3.5.2, Assumption 4.3).

5.2A Gauge Pressure Transmitter (ITT Barton Model 763) 5.2A.1 Reference Accurac

<< Per Ref. 3.5.1, reference accuracy is

<<0.50% of rated span.

This includes the combined effects of linearity, deadband, hysteresis, and repeatability.

PT~ ~ i0.50% Span 5.2A,2 Drift Effects - Per Ref. 3.5.1, drift effect is 11.0% of maximum span per year cumulative.

The transmitters have an 18+25% or 22.5 month calibration frequency.

A two year frequency will be used for conservatism.

PTDH

<<2.00%

Span 5.2A.3 Tem erature Effect. - Per Ref. 3.5.1, the temperature effect is <<1.0% of max span per 100oF.

The normal temperature range is 60'F to 104'F with accident temperatures reaching 120'F [Assumption 4.5).

The uncertainty is calculated as follows:

PT>H ~ <<[((120-60)/100)(1.0%))

Span PT~ = +0.60%

Span 5.2A~4 Radiation Effects Radiation effects are considered small compared to the other effects, so they are considered to be bounded by the other u'ncertainties listed for this instrument

[Assumption 4.3, 4.11).

5 'A.S Static Pressure Effects Gauge pressure is being measured, therefore, static pressure effects do not apply.

5 'A.6 seismic Effect Per Reference 3.1.14, seismic effects are considered to be ~0.5% of span.

<nmo"""~ ~"

PCL 4 +ye I

I TAR/PID No.:

Date:

Date:

CAROLINA POWER fc LIGHT COMPANY CALCULATION SHEET Calculation ID:

HNP-I/INST-1044 Pg.

8 Rev.

0 File:

Project

Title:

Shearon Harris Setpoints Calculation

Title:

RCS Wide Range Pressure:

Accuracy and Setpoint Calculation Status:

Prelim.

Q Final g Void Q 5 'A.7

'c power Su 1

Effect Per Ref. 3.5.1, the power supply effect is t0.025% of span per volt variation.

For a voltage regulation of kl volt [Ref. 3.5.3], the power supply effect is calculated as follows:

PT~< = k [ 1

~ 0. 025% ) Span PT~E

~0. 03t Span 5 'A.8 Humidit Effects These effects on the transmitters are not considered since the transmitters are expected to operate within their reference accuracy for 0-100% humidity conditions

[Ref. 3.5.1).

5 'A.9 Measurement snd Test E i ment Inaccuracies The calibration of this instrument depends on two MQTE accuracies

[Ref. 3.6, Assumption 4.10].

A pressure gauge is used to measure the input pressure and a digital multitmete'r is used to measure the output voltage during calibration.

PTMTBn RO'50%

Span PT~< = 20 50% Span 5 ~ 2A. 10 Calibration Tolerance - Per Ref. 3.6, the allowable range at 5v is 5.00 i 0.02v, for a 1v to 5v signal.

This uncertainty will be applied as a positive and negative bias, because the transmitter is shifted in a known direction.

Converting this to percent span is as follows:

PTCI

+[0.02 / (5-1)

~

100%J Span PTCI ~ +0.50%

and -0.50%

Span 5.2B Gauge Pressure Transmitter (Tobar Model 32PA2) 5 'B.1 Reference Accurse

- Per Ref. 3.5.1, reference accuracy is i0.20% of calibrated span.

This includes the combined effects of linearity, deadband, hysteresis, and repeatability.

PT~ ~ +0.20%

Span

~i

~'4pr4 4

~

TAR/PID No.:

Date:

Date:

CAROLINA POWER 4 LIGHT COMPANY CALCULATION SHEET Calculation ID:

HNP-I/INST-1044 Pg. 9, Rev.

0 File:

Project

Title:

Shearon Harris Setpoints Calculation

Title:

RCS Wide Range Pressure:

Accuracy and Setpoint Calculation Status:

Prelim.

P Final g Void Q 5 ~ 2B ~ 2 Drift Effects Per Ref. 3.5.1, drift. effect is 10.20% of URL for 6 months.

The transmitters have an 18+25% or 22.5 month calibration frequency.

A two year frequency will be used for conservatism.

PTDH =

[4'2 '.20%)

]

Span PTDH ~ E0.80%

Span 5+2B.3 Tem erature Effect Per Ref. 3.5.1, the temperature effect is R1.0% per 100'F at the maximum span (100%)

and

<<3.5% per 100'F at the minimum span (40%).

The normal temperature range is 60'F to 104'F with accident temperatures reaching 104'F [Assumption 4.5].

Using linear interpolation for the calibrated span (50%) the uncertainty is calculated as follows:

PTTH = <<((104-60)/100)[3.5-(3.5-1)(50-40)/(100-40))

Span PTTH ~ <<1.36't Span 5.2B.4 Radiation Effects Radiation effects are considered small compared to the other effectsi so they are considered to be bounded by the other uncertainties listed for this instrument

[Assumption 4.3, 4.11].

5 ~ 2B ~ 5 Static Pressure Effects - Gauge pressure is being measured, therefore, static pressure effects do not apply.

5+2' Seismic Effect Per Reference 3.1.14, seismic effects are considered to be ~0.5% of span.

PTSH = i0.50%

5 F 2' Power su 1

Effect - Per Ref. 3.5.1, the power supply effect is (~0.005% of calibrated span per volt variation.

For a voltage regulation of <<1 volt [Ref. 3.5.3], the power supply effect is calculated as follows:

PTPSH = k[1

~ 0.005%)

Span PTpsE

= +0.01'h Span 5 'B.S Humidit Effects - These effects on the transmitters are not considered since the transmitters are expected to operate within their reference accuracy for 0-100% humidity conditions

[Ref. 3.5.1].

Chr

~.~R bv ~

TAR/PID No.:

Date:

Date:

CAROLINA POWER fc LIGHT COMPANY CALCULATION SHEET Calculation ID:

HNP-I/INST-1044 Pg.

10 Rev.

0 File:

Project

Title:

Shearon Harris Setpoints Calculation

Title:

RCS Wide Range Pressure:

Accuracy and Setpoint Calculation Status:

Prelim.

P Final ~

Void P 5.2B.9 Measurement and Test E i ment Inaccuracies The calibration of this instrument depends on two MGTE accuracies

[Ref. 3.6, Assumption 4.10].

A pressure gauge is used to measure the input pressure and a digital multitmeter is used to measure the output voltage during calibration.

PTMYEin

+0 50't Span PTMrE < ~ i0.50't Span 5.2B. 10 Calibration Tolerance - Per Ref. 3.6, the allowable range at 5v is 5.00

~ 0.02v, for a lv to 5v signal.

This uncertainty will be applied as a positive and negative bias, because the transmitter is shifted in a known direction.

Converting this to percent span is as follower PT~ ~ k[0.02 / (5-1)

~

100%)

Span PTCZ = +0.50% and <<0.50%

Span 5.3 Signal Isolator (Westinghouse NLP2, NLP3) 5 3 ~ 1 Reference Accurac

- As Stated in Ref. 3.5.3, the reference accuracy of this instrument is ~0.1% of span.

PYRA = i0.10't Span 5.4 Pressure Switch (Westinghouse NALl) 5 ~ 4 ~ 1 Reference Accurac As stated in Ref. 3.5.3, the referen'ce accuracy of this instrument is 0.35% of Span.

PSRA = i0.35't Span 5.4.2 Measurement and Test E i ment Uncertainties The calibration of this instrument depends on one MGTE accuracy

[Ref. 3.6, Assumption 4.10).

A digital voltmeter is used to measure the input voltage.

PSMITH; = R0.50'%pan

Cnmngted r i<or\\

TAR/PID oo.:

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CAROLINA POWER Sc LIGHT COMPANY CALCULATION SHEET Calculation ID:

HNP-I/INST-1044 Pg.

11 Rev.

0 File:

Project

Title:

Shearon Harris Setpoints Calculation

Title:

RCS Wide Range Pressure:

Accuracy and Setpoint Calculation Status:

Prelim.

Q Final g Void Q 5.4 '

Calibration Toleranca As assumed in future Ref. 3.6, the allowable range is 5.00 k 0.02v, for a 1.00v to 5.00v signal.

This uncertainty will be applied as a positive and negative bias, because the level switch is shifted in a known direction.

Converting this to percent span is as follows:

PSCY = 4[0.02 / (5-1)

~

100%]

Span PS~

= +0.50% and -0.50%

Span 5.5 Loop effects 5'.1 Insulation Resistance Effects IR effects are not considered, due to the fact that ecyxipment and cables are not exposed to a harsh enough environment to cause noticeable IR effects.

5'.2 Rack Drift Per Ref. 3.5.5, the rack drift is 11.00% of

span, which accounts for the combined drift of all the rack components.

RD = ~1.00%

Span 5 ~ 5 ~ 3 Rack Tem erature Effect Per Ref. 3.5.5, the rack temperature effect is +0.50% of span, which accounts for the combined temperature effects of all the rack components.

RTE = 50.50%

Span

r.mc ':e"

~'4onQp4 I;~ ~ ~

I TAR/PID No.:

Date:

Date:

CAROLINA POWER fc LIGHT COMPANY CALCULATION SHEET Calculation ID:

HNP-I/INST-1044 Pg.

12 Rev.

0 File:

Project

Title:

.Shearon Harris Setpoints Calculation

Title:

RCS Wide Range Pressure:

Accuracy and Setpoint Calculation Status:

Prelim. 0 Final g Void Q 6 ~ 0 CALCULATION OF UNCERTAINTIES 6.1 Table of Uncertainties RCS Wide Range Pressure Channel:

0-3000 psig TABLE OF UNCERTAINTIES

Uncert'ninty, Par'aactcr'

;

.Percent

; of,'

.Span'

:::::::::;:::.":::::;:::::::."

,::,': 'aRiindoii."",'.",".",':;:;.".",':::,'+Bias."..".."..;.';.",."..;.'. ',.",;.",.",.'-.,Bias

."..",."..',".'iu'ge:Presiure:Transaitter

":'HATT:Sa'rton':Nodel':763:::::;:,:::: ':::::

Ri.'ference A'ccu'r'acy Dr.ift Temper'atur'e'eismic Poi7er,". Relil'atTon ICTUS in:,'.

H&TEout Ci'l'db'riti'ori':Tb l'eranciei SighaU:::1'sol'i'to'r'."::::::: Mestin'gho'use'::Model::::kt'PZ':::::Ql'P3::::::::::::::::::::::::::::::::::::.

R'e'fiir'en'ca::

'A'ccur'icy'r'es'sure:::

Suit'ch

':::: Me'sfiiighou'se:'ih'xhil::::)NL1'".:::::::::::::::::::::::::::

Refi;r'e'n'c'ii': A'c'ciir'iicy.'."".

N&TEih Cal'ibrat'ion s0.50 s2.00

%0.60 s0.50 s0.03 t0.50 s0.50 a0.10 s0.35

- s0.50

+0.50

+0.50

-0.50

-0.50 Rack: Drift Rack'TeeIperature s1.00 s0.50 Grand.Tote ls'f,':(Randai),,:

Cr'and:::Total's:::bf,"Rii'ndaiii::.an'd;:Bia's':

x6.9934 s2.64

+1.00

-1.00

Chan'nel.:::Total'R's'ndo'in)+(Bias>'

s3.64

@ban 4~8 4

~

Dat,e:

Date:

CAROLINA POWER tc LIGHT COMPANY Calculation ID:

HNP-I/INST-1044 Pg.

13 Rev.

0 TAR/PID No.:

CALCULATION SHEET File:

Project

Title:

Shearon Harris Setpoints Calculation

Title:

RCS Wide Range Pressure:

Accuracy and Setpoint Calculation Status:

Prelim.

Final g Void Q 6.2 Total Uncertainties The following uncertainties will be used to calculate setpoints.

The uncertainties given are equal to or more conservative than the actual uncertainties.

6.2.1 The total uncertainty for the Alt MiniFlow Open/Close Permissive Bistable Channel is as follows'BCU1

= i3.64%

~ f109 psig 6.2.1 The total uncertainty for the Low Pressurizer Pressure SI trip is as follows [Ref. 3.8.4]:

TBCU2 ~ i10.9%

~ i87.2 psig < 290 psig It is conservatively assumed for the purpose of this calculation-that the uncertainty of Permissive P-11 is bounded by the uncertainty for Low. Pressurizer Pressure SI trip after review of the loop diagrams and accuracy calculations

[Ref. 3.1.25, 3.1;26, 3.1.27, 3.1.28, 3.8.3 Safety Analysis].

When the alternate miniflow open permissive is to reset and close, uncertainties (environmental, etc.)

considered in the P-ll Permissive are considered much less than the Low Pressurizer Pressure SI trip uncertainties.

6.3 High Alt MiniFlow Open Permissive Setpoint - Per Assumption 4.13, the maximum RCS pressure allowed with no alternate miniflow is 2419 psig.

The uncertainty associated with the alternate miniflow bistable will be subtracted from 2419 psig to provide the pump required flow of 60 gpm.

SP

= AL,(+TBCU1 + margin)

SP

~ 2419 - (109

+ 10)'

2300 psig SP ~ 2300 psig Open Permissive for Alternate MiniFlow MOV

~mme)uted Chppv 1

TAR/PID No.:

Date:

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CAROLINA POWER fe LIGHT COMPANY CALCULATION SHEET Calculation ZD:

HNP-I/INST-1044 Pg.

14 Rev.

0 File:

Project

Title:

Shearon Harris Setpoints Calculation

Title:

RCS Wide Range Pressure:

Accuracy and Setpoint Calculation Status:

Prelim.

Final g Void P 6.4 Low Alt MiniFlow Close Permissive Setpoint Alternate miniflow is not desired at pressures where the PORVs may be open.

Permissive P-11 insures that the PORVs will be closed when the Pressurizer pressure drops below 2000 psig.

Therefore, the alternate miniflow line must not close until RCS pressure is below the point at which Permissive P-11 actuates.

Although there is a head difference (somewhere between 5~20 psig) between the Pressurizer Pressure channel and the RCS Pressuie channel, it is in the conservative direction and may be considered as additional margin (Assumption 4.14].

The uncertainty associated with the alternate miniflow bistable will be subtracted from the 2000 psig P-ll setpoint along with pressurizer pressure Permissive P-11 uncertainty to make sure the alternate miniflow MOV does not close before the PORVs close.

SP SP

~ AL + (-TBCU1 + -TBCU2 + margin)

~ 2000

+ (-109

+ -90

+ -51)

= 1750 psig SP = 1750 psig Close Permissive for Alternate MiniFlow MOV Per Ref. 3.8.3's Safety Analysis, the setpoint of 1750 psig is conservative with respect to the closure of alternate miniflow MOVs to provide the required safety injection.

Cnm 1 Checkedi I TAR/PID No ~

I Date:

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CAROLINA POWER 4 LIGHT COMPANY CALCULATION SHEET Calculation ID:

HNP-I/INST-1044 Pg.

15 Rev.

0 File:

( Project

Title:

Shearon Harris Setpoints Calculation

Title:

RCS Wide Range Pressure:

Accuracy and Setpoint Calculation Status:

Prelim.

Q Final g Void Q 7 0 FIGURES 7.1 Setpoint Diagram (AL) 2419 psig (60 gpa Required Flou)

>Alt HiniFlow Bistable Channel Uncertaint

>~Her in (SP) 2300 psig Alt HiniFiow Open Permissive (AL) 2000 psig (P-11 Permissive)

>Alt HiniFlou Bistable Channel Uncertaint

>P-11 Bistable Channel Uncertaint

>Harclin (SP) 1750 psig Alt Hiniflmr Open Permissive

snoot

~@4 L ~

II ~

I r

CIl liar's Lot+

TAR/PZD No.:

Date:

Date:

CAROLZNA POWER a LIGHT COMPANY CALCULATZON SHEET Calculation ZD:

HNP-Z/ZNST-1044 Pg.

16 Rev.

0 File:

Project

Title:

Shearon Harris Setpoints Calculation

Title:

RCS Wide Range Pressure:

Accuracy and Setpoint Calculation Status:

Prelim.

Q Final g Void Q 7.2 Train A RCS Vide Range Pressure Loop Diagr~

Reactor Coolant System Hot Leg Loop 3 RVLIS Sensor Bellows LE-01RC-1310 SAV 0 3000 psig RVL IS Hydraulic Isolator LIB-01RC-1310 SAV 0 3000 psig Pressure Transmitter PT.01RC-402 IV 1.5 vdc Loop Power Supply (Hon-Isolated)

PQY-402 0 10 vdc Signal Isolator PY-402C 0 10 vdc Signal Cooperator PS-01RC-402 A1 Set at 2300 psig Reset at 1750 psig Aux Relay PY-402A3 Normally Open Contact Open / Close Permissive Alternate Hini-Flow HOV Train A SSPS

( +moi cod Date:

CAROLINA POWER 5 LIGHT COMPANY Calculation ID:

HNP-I/INST-1044 Date:

CALCULATION SHEET Pg.

17 File:

Rev.

0 Project

Title:

Shearon Harris Setpoints Calculation

Title:

RCS Wide Range Pressure:

Accuracy and Setpoint Calculation Status:

Prelim.

P Final g Void P 7.3 Train B RCS Wide Range Pressure Loop Diagram Reactor Coolant System Hot Leg Loop 1

RVLIS Sensor Bellows LE-01RC-1320 SBN 0 3000 psig RVLIS Hydraulic Isolator LIB.01RC-1320 SgiI 0 3000 psig Pressure Transmitter PT-01RC-403 IVM 1-5 vdc Loop Pouer Supply (Isolated)

PQY-403 0 10 vdc Signal Comparator PS-01RC-403 8

Set at 2300 psig Reset at 1750 psig Aux Relay PY.403B Normally Open Contact Open / Close Permissive Alternate Hini-Flou HOV Train B SSPS

Cc PQ~plr~

~ 4

~

TAR/PID No.:

Date:

Date:

CAROLINA POWER Sc LIGHT COMPANY CALCULATION SHEET Calculation ID:

HNP-I/INST-1044 Pg.

18 Rev.

0 File:

Project

Title:

Shearon Harris Setpoints Calculation

Title:

RCS Wide Range Pressure:

Accuracy and Setpoint Calculation Status:

Prelim.

P Final g void P 7.4 Memo From HESS/Mechanical on CSZP Pump Protection High RCS Pressure Setpoint September 25, 1992 MEMORANDUM T~

FROM:

The maximum Reactor Coolant System pressure which will ensure protection of the weakest charging/safety injection pump (CSZP) during two pump operation in the injection mode of SZ is 2419 psig.

This value should be used in your calculation of alternate miniflow MOV opening setpoint in PCR-6547 (Alternate Miniflow Re-design).

This value includes allowance for: head loss through the SZ system piping to the RCS cold legs, head loss from the SZ injection points in the cold legs through the reactor vessel to the hot legs, and head gain between the RWST elevation and the cold leg connections.

A system configuration was assumed with the strongest and weakest pumps opertating in parallel at present performance characteristics.

DISCIPLINE DESIGN VERIPICATION RECORD I.

]nstrcs:time to Verification Persocnel Page 1

Plant SHw t'P Project E~ o/

LCS File Ko.

g Io-ZF7-)O D~~t Ko.POP-2 r- 0 Rev C7 a

level W

0 (Class A)

[ ] Seismic (CLass 8)

[ )

FP.D (Class O)

[ ] Other Design verification should be done in accordance

<<1th AKSl K45.2.11, Section 6, as smencied by Regulatory Guide 1.61, Rev. 2.

Special instructions:

Discipline.Project Engineer ll.

Verification Dcxx~tation Applicsbi l ity Disci line Hechsnical KVAC Electrical

]AC Other Disci line Civil Structural Seismic Equip. Dual.

Civil Stress Fire Protection Envirormentsl Qualification Kcmcsn Factors Haterials

[][][][][][][][)[]

Verification Hethods Used:

W Design Revie<<

[ ] Alternate Calculations

[ ] qualification Testing Design Oocunent AcceptWcey Design Verifier~

Ko, ccccments st tsched Date Ackno<<ledgement of Verification:

Date zj ll]. Resolution of C~tst Ccmcsenty P>>-c v. '"~

-bed) t (RE)

ActioJYtsken makes of icu( nWi Design Verifier (OPE)

Date Date zl 2

zJpz KED Procedure 3.3/Rev.

50

Page 2

Plant DISCIPLIKE DESIGK VERIFICATILA RECITED CONHEHT SHEET K&iUPP File Ho.

Project M

AC p-z- ~~r'-)~Vg Docuwnt go. PIAIPZ+I TIO'Y Rev 0

This sheet is only required shen contents are being made.

Ccaaent Ho.

Comnent

~PE gEV/a(oK L.E.V

c. Fo4 E,I-. 8.

~ 4 %4doLD bG.

15 ORc 5-TG. gF FEgBNC& ~o 3 ~ ZcG /PJ

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2 (1 z, Zl Z.

2/

Z

/u/gz.

Zl/g'~

z/ly'z HED Procedure 3.3/Rev.

50

Page 1

DESIGN REVIEW CHECK SHEET Plant

~h NP'ocument Type 6

LCUl A7/de ProJect ~+~ /U7 A ~~

Document No.

NP-~ ~/US~- yy File No.hN/-X 57- >~~

Revision

==

Description:==

Mark each item yes, no, or not applicable and initial each item checked by you.

1.

Were the inputs correctly selected and incorporated into design?

2. Are assumptions used in the design adequately described and reasonable?

gES

(

~&5 NOTE:

Review shall include but is not limited to applicable inputs specified in NED Procedure 3.1.A, paragraph 3.1.A,4.

3. Are the appropriate quality and quality assurance requirements specified?

4, Are applicable

codes, standards, and regulatory requirements including issue and addendum properly identified, and are their requirements for

~

~

~

~

design met?

5.

Has applicable construction and operating experience been considered?

6.

Have design interface requirements been satisfied?

7.

Was an appropriate design method used?

8. Is the output reasonable compared to inputs?

~ES

$65(

yE.&(

gES

9. Are the specified parts, equipmen-.,

an rocesses uitable for the application?

yes

10. Are the specified materials compatible with each other and'he design environmental conditions to vhich the materials vill be exposeds

~

'~/I'ED Procedure 3.3/Rev.

50

Page 2

Document Type

.!~ t'1 11.

Have adequate maintenance features and requirements been specified?

12.

Are accessibility and otter provisions adequate for performance of maintenance,

repair, and any expected in-service inspectional

+

hf A'3.

Has the design properly considered radiation exposure to the public and to plant personnel (ALARA)?

~ES 14.

Are acceptance criteria in the design documents sufficient to allow verification that'design requirements have been satisfactorily accomplished?

15.

Have adequate preoperational and periodic test requirements been specified?

16.

Are adequate storing, handling,

cleaning, shipping, and identificati n requirements specified?

~

~

17. 'Are requirements for record preparation, review, approval, retention, etc.,

adequately specified?

~Q(

18.

Have all problems with this design known from prior application been considered and resolved?

2 I&a For each question on the check list not answered

yes, explain belo~.

If "Not Applicable" give reason.

Signature (Design Verifier)

+ h14 Eau(PH&V7, eeet orUEA/7, oX WPi&A/AL i5 XQS7ALCED, /VOGIE/GD

> D/Z 7857 GD 85 y p 7+is 0gac c L+77oAJ.

Date NEO Procedvre 3.3/Rev.

50

Design Package Setpoint Worksheet Mod. No.

Field Rev.

Page No.

~PC -6 47 PS-0 RC-402 TAG NUMBER INSTRNIENT SPAN 0-3000 PSIG SET POINT FUNCTION RCS PRESSURE ALT NINI-FLOM PERNISSIVE REFERENCE DOCQIENTS AHD NOTES PCR 6547 "CS P ALTERNAT NINI FLOU CALCULAT ON HNP-I INST-1044 SET RESET SET RESET SET RESET SET RESET S/R POINT 2300 1750 UNITS PSIG PSIG SET POINT TOLERANCE x15.0 F15.0 ACTION INCR DECR FUNCTIONAL DESCRIPTION OPEN/CLOSE PERNISSIVE FOR NOV 2CS-V757SA-1 OH HIGH/LSI RCS PRESSURE CHECKED BYi 6476 8-2G'-

E REV DATE REV DATE

Design Package Setpoint Worksheet Mod. No.

Field Rev.

Page No.

PCR-6547 0

S-0 C- 03 TAG NUMBER INSTRUNENT SPAN 0-3000 PSIC SET POINT FUNCTION S/R POINT UNITS SET'OINT TOLERANCE ACTIOH 1

RCS PRESSURE ALT HINI-FLOU PERNISSIVE REFERENCE DOCUNEHTS AND NOTES PCR 6547 <<CS P ALTERNATE NINI FLOU CALCU AT OH HHP-INST-'1044 SET RESET SET RESET SET RESET SET RESET 2300 1750 PSIC PSIG a15.0 a15.0 INCR DECR FUHCTIOHAL DESCRIPTION OPEN/CLOSE PERNISSIVE FOR NOV 2CS-V759SS-1 OH HIGH/LOU RCS PRESSURE DATE 8 24 FZ REV DATE REV DATE

Des ign Package Cov'er Sheet lVM. Na.

KR-6547 Field Rev. hb, 0

DESIGN DOCUMENTATIONREVISIONS

Form 6

DRAWING REVISION SHEET MOD NO.

PCR-6547 FIELD REVISION NO.

0 PAGE NO.

DRAWING- ':

NUMBER ":,

DRAWING TITLE UPDATE BEFORE OPERA-

BILITY "RECORD OF REVISION 2166-B-401, S317 2166-B-401, 8319 1364-46574, S22 1364-46577, S8 2166-S-PRC0402 2166-S-PRC0403 1364-1328, S29 1364-10929i S2 1364-10929, S5 1364-51840 1364-92103 1364-51837 1364-2776'26 1364-2776, S28 1364-45841, S59 1364-45841, S58 1364-37747 1364-2776, S30 1364-45841, S49 1364-37746 2166-B-432 2166-B-508 CVCS MINI-FLOW VALVE 2CS-V757SA-1 CWD CVCS MINI-FLOW VALVE 2CS-V759SB-1 CWD PZC CAB 1 INTERCONNECTING WIRING PZC CAB 4 INTERCONNECTING WIRING RCS WIDE RANGE PRESSURE LOOP 3

RCS WIDE RANGE PRESSURE LOOP 1

PROCESS CONTROL SYSTEM BLOCK DIAGRAM NSSS PCE EXT CONNECTION DIAGRAM NSSS PCE EXT CONNECTION DIAGRAM PRINTED CIRCUIT CARD LIST CAB 1

NSSS PIN ASSIGNMENTS PRZNTED CIRCUIT CARD LIST CAB.

4 SSPS-INTERCONNECTING DIAGRAM SSPS-INTERCONNECTING DIAGRAM SSPS-SCHEMATIC DIAGRAM SSPS-SCHEMATIC DIAGRAM SSPS OUTPUT CAB 2 WIRING LIST SSPS-INTERCONNECTING DIAGRAM SSPS SCHEMATIC DIAGRAM SSPS OUTPUT CAB 1 WIRING LIST SHNPP INSTRUMENT LIST SHNPP SETPOINT DOCUMENT NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NPMP - REV. 4

DRAWING REVISION SHEET Form 6

MOD NO+

PCR-6547 FIELD REVISION NO.

0 PAGE NO.

."'RAWINGj~$$

"":-" "-NUMBER'~9i:;",i 2166-S-2020 S28 LIMITORQUE WIRING DIAGRAM UPDATE ~p>

-.BEFORE

,:OPERA-,wi

'.BILITY,:),"::;

NO

~RECORD 'OF';

Jr~REVISION ~~";:

R'-" "::::.":;:, '"'.":

• For later use in tracking completion of the revision.

NPMP - REV. 4

Form 6

DRAWING REVISION SHEET MOD NO.

FIELD REVISION NO.

0 2165-G-804 CVCS FLOW DIA.

@!%<M;S~'<'!'l

'UPDATE:i:::4

BEFORE!.,>

CBILITY~~e

.YES

)g+RECORD","'OF/

.kijREVISION'.'jj~:";

2165-S-1304 CVCS SFD YES 2165-G.805 CVCS FLOW DIA.

YES 2165-S-1305 CVCS SFD YES 2165-G-140 2165.G-141 CVCS RAB PLAN CVCS RAB SECTIONS NO NO 1364-96842 SI/CHARGING PUMPS MINI-FLOW STRAINER 1364-42815 MINI-FLOW ORIFICE ASS'Y NO NO 1364-B-069 1364-B-070 1CS-650 1CS-651 1CS-150 1CS-151 1CS-152 2166-B-043S01 SHNPP VALVE LIST SHNPP LINE LIST SOUTHWEST FAB. ISO II a

II N

II N

N II CABLE AND CONDUIT LIST NO NO NO NO NO NO NO NO 2166-G-322 RAB CONDUIT, TRAYS 6 GROUNDING EL. 305'HEET NO 1 UNIT 1 2166-S-2530 MLA 2166-S-2530 MLB 2166-S-2530 011'1 MEQ LIST MEQ LIST MEQ LIST NO NO NO 1-CS.H-4400 PIPE HANGER DRAWINGS NO 1-CS-H-4403 1-CS-H-'4406 1-CS-H-4609 1-CS-H-4610 II II II tl II II NO NO NO NO 1364-93934 VOGT VENDOR DRAWING FOR 3/4" VALVES 2.l(p>-5-2><<Co~

~n.~~

e Lc J e.l, G <'+

C rGQBg Vg ll/e 4

w<<P C ~

e NO NPMP - REV. 4

Form 7

DESIGN DOCUMENT REVISION SHEET MOD NO.

FIELD REVISION NO.

PAGE NO.

';:;:,DOCUMENT;,.",I:;,';""

UME UPDATE.i-"-',

BEFORE~~,

OPERA =."'~

'BIL'ITY

"'-+RECORD

'-'OF

<'"IREVISION "

1-CS-H-4235 PIPE HANGER CALCULATION 1-CS-H-4271 1-CS-H-4233 1-CS-H-4225 1-CS-H-4268 1-CS-H-4231 1-CS-H-4227 1-CS-H-4229 1-CS-H-4544 1-CS-H-4272 1-CS-H.4226 1-CS-H-4243 1-CS-H-4274 1-CS-H-4261 1-CS-H-4247 1-CS-H.4255 1-CS.H-4266 1-CS-H-4257 1-CS-H-4259 1-CS-H-4251 1-CS-H-4253 1-CS-H-4249 1-CS-H-4245 1-CS.H-4241 1-CS-H-4237 1-CS-H-4239 1-CS-H-4609 1-CS-H-4610 NO N

• For later use in tracking completion of the revision.

NPMP - REV. 4

Form 7

DESIGN DOCUMENT REVISION SHEET MOD NO.

7 FIELD REVISION NO.

PAGE NO

~UPDATE

~~.'BEFORE

'OPERA-.;P>~

'.BIL'ITY.',"

h

-<,~RECORD'F.".,:.

.j ":.REVISION

~~'-CS-H-4403 PIPE HANGER CALCULATION 1-CS-H-4406 1-CS-H-4400 1-CS-H-4420 NO 141-1A 141-1 141-2 DAC-1 E-6001

• CS-0021

• CS-0022 DBD f104 PIPE STRESS CALCULATION AUXILIARYSYSTEM LOAD STUDY LOAD FACTOR STUDY FOR SHNPP MECH. ANAL. AND CALC.

FOR 1CS-746 MECH. ANAL. AND CALC.

FOR 1CS-752 SAFETY INJEJCTION SYSTEM DBD NO NO NO NO NO

• For later use in tracking completion of the revision.

NPMP - REV. 4

DRhWING NO. 2166-S-2530 SHEET NO. //I 1

g/8 Z

REVISED PER PCR-4850

,NO.

DhTE REVISION CP&L -

NED - DRYING REVISION BY CK hPPVD (5444MED ~ HNP)

~ ~

g)EC,B7'E /=go<

2/6,(o 253oj 0/II p& PdA-65q7 SHEARON HARRIS NUCLEAR POMER PLANT tKCHANICAl. KOUIPl%NT KNVIRONlKNTALOlJALEFICATZON PROGRAM t k%0)

COMPONENT KVAl.UATIONREPORT I

CHEC

$T Nag ill NgUFACTUgfgg cRosBY vhlya 6 chcB co.

g5fg go,g ~ll'->>-65 SYSTE%

Chemical

& volume Control VfgQQQ PQQ gO g

1364-53896/so 0

EOULPt%HT Relief Ualvea

$.96/KLEVa VALVE 1407 ORM A - Ea rPMENT EMVIRONMENTAt. CON01TIONS PNQkCTER TED'EIATUAE t Fal tltKSSUAE t PSIQ CHEICCALS AVIATION l AADQ

~AGENCY t FT)

OPERASILITV tAOCE CONOITION 130 2712 NOR~ NSIENT ONTION 104 VALVE

!NE LIST OWL 1

MLS h SW h

'IP 5-1 Table 1-2

+ f2 (+5) 10 YAS 3 ill 4 hB21-h, B FShR g.)I.C Q5h AtSIEMT CORDITION

++

130

'AYH O'NL" 1364-53215 8/h 1 Yr, N/h, I~ fllLll0 23 4+~89 hB21"R4oR5

$tEFKAKNCK CODE No, ISO'fC Llit 2-F5' 3.JJ. Q Fs~ 3.)le I~ F!0 Lilt 23 hB21-R4,R5 FSqg 3 /)B PSAR Section CUAt.IFICaTtoM STATUS'E.VIS PA ED 8'fs CKKD BYs ORBJJULJJl OATfs~~~~-85 Pggfg 1-30-85, 8-15-85 C08%NTQ Part 0 4 0 OOOO 000000000OO A AN 0000000004001 bio cAXF z~

0e 00000 OO OOOQOOO e Qo

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OOIOOOAOOOOOOOI

~~ gogS7 gt9S+ pb~E' o+/

ME HAINTENAHCE ACTIVITIES CQBLF12 CHE LIST XO.: ill HSSS HAHUFA URER:

Crosb Valve 4 Ca e Co.

~

MODEL HO ~ :

JLT-JB-65-TD YENDDII II RL:

NJS EEDIPNENT TYPE:,Relief Yal ea VALVE/EQUIP.

TAC NOD'CS R557SN I (IC 744) 2CS-RSSBSH-I (ICS-755)

Enteree on EDSS~

Date A/B~

PERIODIC/REPLACEMENT MAI ANCE:

I 2 ~

3 ~

4 ~

Part

~Deseri tion None Required CPAL Part No.

Repla ment Int val Renarka Patch Tech Ra Dar.e C,

MAINTENANCE CYCLE START DATE:

Fuel Load D/K.

INSPECTION/REFURBISHHEHT RE EMENTS:

Hone Required Prepared:

Revievcd:

g

~

r Approved:

4 Date:

Date:

Date:

<</c/~

NR1-055 S

62 11-15 CHECKLIST 4 EBASCO TAG NO.

CPbL TAG NO MEQ-:i~>S-ML-A SYST EQU SPECIFIC IO HAN COMPONENT TYPE 6 0004 HQ0213 MQ0109 MQ0109 2CS-R521SN-I 2CS-R522SA-I 2CS-R52358-I ICS-127 ICS-290 ICS-293 BJS BJS CS-R522SA CS-R52358 FAU FAU 2060 2060 JA CSIP SUCTION FROI4 RHR REL IE 8 CSIP SUCTION FROM RHR RELIEF 2060 FAU CS-R52 ISN BJS VCT RELIEF VLV 9

ld 1l 12 13 14 15 ld I7 18 l9 20 21 21 23 24 I

Qo I

2 HQ0024 MQ0024 C -

4

-I 2 5-75

-R 8

-I 2

5-VSO ISN-I 2CS-V502SN-I 2CS-V503SN-I MQ0025 MQ002 I MQ0028 HQ0017 MQ0098 HQ0085 MQ0020 MQ0020 2CS-V513SA-I 2CS-V514SN-I 2CS-V515SN-I 2CS-V516SA-I 2CS-V51758-I 2CS-V51858-I 2CS-V519SN-I 2CS-V520SM-I HQ0025 2CS-VS I ISA-I MQ0025 2CS-V512SA-I CS-V502SN CS-V503SN CS-VS I ISA CS-V512SA CS-VS'13SA CS-V514SN CS-VS ISSN CS-V516SA ICS-492 ICS-480 ICS-7 ICS-B 2060 HNK TE'Ronj o6o INK yg-5,-gpss AH 60 HOC A~cR W5'gq oeo

>i~oc ICS-9 ICS-459 ICS-477 ICS-410 HNK llNZ INK 2060 2060 2060 ICS-472 ICS-11 ICS-355 ICS-396 2060 2060 2060 2060 INK HNK 1 INK INK CS-V51756 CS-VS IBSB CS-VS 19SM CS-V520SN IC 20

~Gjj C

I

-744 060 FAU 5-R55 N

5-755 206 AU CS-R 8SN lc -

7 200 HC-5 JS 8

5 BJ NORMAL CHARGING LINE I SOLAT ION ERNATE CHARGING LINE ISOLAT 5

NORM LTOW ORIFICE A CIV 5

NORM LTDM ORIF ICE 8 CIV CVCS NORM LTDN ORIF ICE C CIV RCPS PI SEAL WATER BYPS ISOL V NORl4 CHARGING LINE CK VLV CLV RCP SEAL VTR RET INSIDE ISOL V RCP SEAL VTR RET OU'TSIOE LSOL CVCS NORM LTON ISOL CIV A RCP PI SEAL WATER RETURN ISO 8

RCP tj SEAL LEAKOFF LSOL VLV BJT BJT ALT BJT CVC BJT CVC BJT BJT Bcc BBL BBL BJT 8JT BJI RELIEF L

1AR INQ U

5 EFUE WA R

Gl R

LIN VA CVCS SSURIZE SPR L

25 28 27 28 29 30 31 31 33 34 35 38 37 38 39 40 41 41 43 44 45 48 47 48 49 50 53 51 53 54 55 58 57 58 59 80 HQ0020 HQO097 MQ0097 MQ0097 MQ0125 HQ0125 MQ0125 MQ0125 MQ0125 HQ0127 MQ0132 MOO 1 98 MQ0202 MQ0199 HQ0139 1400108 HQ0107 MQ0107 MQ0 107 MQ0107 l400064 MQ0064 MQ0064 HQ0063 HQ0063 MQ0063 l400062 2CS-V521SN-I 2CS-V52258-I 2CS-V52358-I 2CS-V52458-I 2CS-V541SN-I 2CS-V542SN-I 2CS-V544SN-I 2CS-V545SN-I 2CS-V546SN-I 2CS-V547SN-I 2CS-V552SN-I 2CS-VSBOSN-I 2CS-V582SN-I 2CS-V583SN-I 2CS-V585SA-I ccS V58658-I 2CS-V587SA-I 2CS-V58856-I 2CS-V589SA-I 2CS-V59058-I 2CS-V591SA-I 2CS-V592SAB-2CS-V59358-I 2CS-V594SA-I 2CS-V595SAB-2CS-V59658-I 2CS-V591SA-I MQ0108 HQ0108 MQ0108 2CS-V60056-I 2CS-V60158-I 2CS-V60258-I MQ0115 2CS-V603SA-I MQ0115 MQOI IS MQ0115 2CS-V60458-I 2CS-V605SA-I 2CS-V60656-I 70flM 0113 (OlldR MQ0062 2CS-V598SAB-I HQ0062 2CS-V59958-I ICS-437 ICS-34 1

ICS-382 ICS-423 ICS-16 ICS-22 ICS-31 ICS-35 ICS-43 ICS-102 ICS-28 ICS-319 ICS-123 ICS-167 ICS-214 ICS-278 ICS-110 ICS-168 ICS-169 ICS-171 ICS-173 ICS-201 ICS-187 ICS-178 ICS-206 ICS-192 ICS- '183 ICS-211 IC5-191 ICS-182 ICS-2 10 ICS-196 ICS-219 ICS-217 ICS-218 ICS-220 2060 HNK 2060 HNK 2060 HNK 2060 HNK CS-V521SN CS-V52258 CS-V52358 CS-V52458 CS-V54 I SN 5-V542SN HOG 2060 2060 2060 2060 jjoc C

lloc HOG CS-V544SN CS-V545SN CS-V546SN 2060 1joe 2060 INZ 2060 lNI 2060 HNZ CS-V541SN CS-V552SN CS-V580SN 2060 HMZ 2060 HNZ 2060 lloc 2060 INK CS-V582SN CS-V583SN CS-V585SA CS-V58658 2060 2060 2060 2060 2060 2060 2060 2060 2060 2060 2060 2060 2060 2060 2060 2060 2060 2060 2060 2060 HOH C

HOH HOH 1IOH Ho I lloI HO I INZ IIOK llOK IIOK HOC HOC HOL llOH HOH l loll 1 loll 5-V587SA CS-V58858 CS-V589SA CS-V59058 CS-V59 ISA CS-V592SAB CS-V59358 CS V594SA'S-V595SAB CS-V59658 CS-V591SA CS-V598SAB CS-V59958 CS-V60058 CS-V60 158 CS-V60258 CS-V603SA CS-V60458 CS-V605SA CS.V60658 BJT BBL BBL BBL Bcc Bcc Bcc ecc Bcc Bcc BJT Bcc Bcc Bcc Bcc BBL Bcc Bcc Bcc Bcc Bcc A CSIP SUCTION ISDL VLV Bcc C CSIP SUCTION ISOL VLV Bcc.8 CSLP SUCTION ISOL VLV Bcc Bcc Bcc Bcc BCC A CSIP DISCH CK VLV C CSLP DISCH CK VLV 8 CSIP DISH CK VLV A CS IP 0 I SCH I SOL VLV C CSIP OISCH ISOL VLV Bcc 8

CSIP DLSCH ISOL VLV BBL BBL A CSIP RECIRC LSOL VLV C CSIP RECIRC ISOL VLV BBL '8'SIP RECLR ISOL VLV Bcc A CSIP DISCH X-COMM VLV C CSIP DISCH X-COMM VLV WI TH 1 C CSLP Dl SCH X-CONN VLV VlIH 8 Bcc Bcc 8 CSIP OISCH X-CONN VLV Bcc C RCP dj SEAL WATER RETURN ISO RCP A SEAL INJECT ISOL VLV CIV RCP 8 SEAL INJECT ISOL VLV CLV RCP C SEAL INJECT ISOL VLV CIV REHT HX TCV INLET ISOL VLV REHT HX CV OUTLET ISOL VLV LO HX OUTLET ISOL VLV INLET ISOL VLV TO LD PCV OUTLET ISOL VLV TO LD PCV DEMIN RETURN CK VLV RHR FCV To LO HX 5'V RETURN SPRAY To VCT CK VLV Rc FLTR OUTLET CK VLV VCT OUTLET CK VLV MINI FLOW ISOL VLV EMERG BORATLON FLOW ISOL VLV A CSIP SUCTION X-CONN VLV C CSIP SUCTIOM X-COMM WITH A C C CSIP SUCTION X-COMM Vl TH 8 C

8 CSIP SUCTION X-CONN VLV

E)El ETE'Rc'r 2/(o(u ~) N/ B M RA-(a5q7 CAROLINA PUI LICHT COo KbhSCO SERVICE',iCORPORATEO SHEAROH IlARRIS NUCLEAR POMER PLAHT UNIT I ECHAHICAL EQUIPHEHT (HOH-IK) QUALIPICATIOH (HEQ)

HOH-HKTALLICHATKRIAL PARTS LISTING (HSSS EOUIPHEHT)

HASTER LIST b SHEET 14 0

DEPT 530 CHECK LIST HO.

VALVE/

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PART DESCRIPTIOH I 7 y

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f@C / C'g-gyjr7 40 4'1) 40 40 See C~ent Porn b 40 117 118 3CS-V6825N 2CS-D633SN 2CS-V7575A 2CS-V7605A 2CS-V7SSSb 2CS-V75958 Casket D le phrs go Dieph Supp Sht Shin Masher DRing Packing Casket tlexltaIIIc KPT Polyurethane Polyethylene EPT cAernwrvP t I ex its 1 I ic 40 40 4/0 40 40 40 See Co~nt tora b

119 120 3CC-R135N 3CC-R12SH 3CS-V548SH 3CS-V6SSSH Ho Hon-Hetsllic Parts Casket Plesltallic 40 2526M

Design Package Self-Assessment Records Cover Sheet Mod. No.

PCR-6547 Field Rev.

No.

0 SELF-ASSESSMENT RECORDS

Form 17 ALARA PRE-DESIGN WALK-DOWN RECORD Plant HNP Project No.

RET-P-6547 Mod. No.

P R-6547 Mod. Title ALTERNATEMINlFL W REDESI N

Revision 0

File No.

RET-P-6 47 Scope of IVork This modification consists ofremoving Alternate MiniflowRelief valves 2CS-R557SN-1 &2CS-RSSSSN-1 and replacing with 90'lbows. Two orifices and three site fabricated strainers will be installed upstream of where the relief valves were located. See drawing SK-6547-M-2001.

Cable routes associated with this modification are in non-radiated areas.

The piping changes required by this modification will occur in the room above the CSIP pumps. This will require approximatety 250 manhours to complete this work in this area.

Please provide a manrem estimate and any other ALARAdetails to ensure a good engineered product.

Special ALARAConsiderations

%l

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Ed William.

Design Engine.r P ALARA~ecpuist Installation ~r.pr csentative Date PZ Date 7'"

Date NPMP - REV. 4

COMMENT RESOLUTION FOR ALIVE PRE-DESIGN WlGKDOWN SAFETY INJECTION MINI-FLOW LINE ST INER

~pro otal:

Install large mesh(1/8" holes) strainer on Carp vecircciation line upstream of normal a'nd alternate mini-flow orifices.

Advantacdes:

1 ~

2.

3 ~

4.

Prevents pump damage due to introduction of foreign material that could plug mini>>flow orifices and dead-head pump.

Robinson event illustrates susceptibility in similar pump design.

Cost is low.

Fabrication and installation will not extend outage window.

5.

Strainer area is large relative to required flowthere will be virtually no restriction of flow or pressure drop unless an extremely large amount of material is introduced.

6.

No maintenance or inspection effort will be required strainer mesh will pass all expected fluid contents.

7 ~

Strainer is oriented and located to minimize crud accumulation.

Location is on mezzanine which is not a high traffic area.

s Disadvanta es:

May accumulate some crudpotential hot spot(in low traffic area).

Permanent shielding can be installed at plant request.

DISCIPLINE DESIGN VERIFICATION RECORD 1.

lnatrcatfcra to Verification Perscsnel Page 1

Plant Project File Ho.

Oocuaent Ho.

Rev

)0 Level W 0 (Class A)

[ ] Seiscscc (Class 6)

[ ) FP-0 (Class 0)

[ ) Other Design verification should be done in accordance

<<fth AHst H45.2.11, Section 6, as amended by Regulatory Guide 1.64, Rev. 2.

Special fnstructfonsc Discipline Project Engineer 11.

Verif1cat ion Doccaaentati on Applicability Disci line Hechanical HVAC Electrical IIC Other

[][)[]

M 0 fsci l ine Civil Structural Seismic Equip. Oual.

Civil Stress Fire Protection Environnental Oualitication Hcnan Factors Haterfals

[][][)[)[)[)[)[][]

Verification Hethods Used:

W Design Revfe<<

[ ] Alternate Cafculat>ons

[ ) Oualiffcation Testing Design oocclcent Accus>veh v~ M Ho [ ] - ccnments attached.

Design Verifier Date l 23 2-Ackno<<ledgecccent of Vere '"

e ni<~

111. Resolution of Coaaentst Ccccaents Resolved (See Attached) t (RE)

Actfon taken makes Design Oocuccents Acceptable:

Design Veriffec Date Date (OPE)

Date HFD Procedure 3.3/Rev.

50

Page 1

DESIGN REVIEW CHECK SHEET P'lant Project File No.

Document Type Document No.

Revision

==

Description:==

Mark each item yes, no, or not applicable and initial each item checked by you.

1.

Were the inputs correctly selected and incorporated into design?

2.

Are assumptions used in the design adequately described and reasonable?

NOTE:

Review shall include but is not.limited to applicable inputs specified in NED Procedure 3.1.A, paragraph 3.1.A.4.

3.

Are the appropriate quality and quality assurance requirements spetiiied7

$0'S:.

4.

Are applicable

codes, standards, and regulatory requirements including issue and addendum properly identified, and are their requirements for design met?

5.

Has applicable construction and operating experience been considered?

6.

Have design interface requirements been satisfied?

7.

Was an appropriate design method used?

8. Is the output reasonable compared to inputs?

9. Are the specified parts, equipment, and processes suitable for the application?

10. Are the specified'aterials compatible with each other and the design environmental conditions to which the materials will be exposed?

NEO Procedure 3.3/Rev.

50

Page 2

Document Type Document No.

Revision 11.

Have adequate maintenance features and requirements been specif ied?

12.

Are accessibility and other provisions adequate for performance of maintenance,

repair, and any expected in-service inspections?

g 13.

Has the design properly considered radiation exposure to the public and to plant personnel (ALARA)?

gp 14.

Are acceptance criteria in the design documents sufficient to allow verification that design requirements have been satisfactorily accomplished?

15.

Have adequate preoperational and periodic test requirements been specified?

16.

Are adequate storing, handling,

cleaning, shipping, and identification requirements specif ied?

17.

Are requirements for record preparation, review, approval, retention,

~

~

etc.,

adequately specified?

18.

Have all problems with this design known from prior application been considered and resolved?

For each question on the check list not answered

yes, explain belo~.

If "Not Applicable" give reason.

Signature (Design Verifier)

Date gyp procedvre 3 3/<ev 50

DISCIPLE DESIGN VERIFICATION RECORD l.

Icmtnmti~ to Verification Persornel Page 1

Plant Project File No.

ACf-F'beah Docunent No.

>4-~R-f 5<

Rev 0

Level

+ 0 (Class A)

( ) Seismic (Class 8) f ) FP-0 (Class 0)

[ ) Other Design verification should be done in accordance <<ith ANSl N45.2.11, Section 6, as anenoed by Regulatory Cuide 1.64, Rev. 2.

Special instructions Discipline Project Engineer 11.

Verification Docueentation Applicability Disci line Nechani eel HVAC Electrical ICC Other

[)()

(3 Disci line Civil Structural Seismic Equip. 0uel

~

Civil Stress Fire Protection Environeental Dualification Huren Factors Haterials I )()

(3()

I)

(3()()

Verification Methods Used:

Pg Design Revie<<

( ) Alternate Calculations

( ) qualification testing Design Doom>>nt Acceptable,:

Design Verifier No ] ). cceo>>nts attached.

SA Date

/5 - '7l Ackno<<ledganent n4 <<->>'cati~.

(OPE)

Date 111. Resolution of Ccmmsrtst Ccec>>nts Resolved (See Attached):

(RE)

Action taken makes Design Oocueents Acceptable:

Design Verifier Oa'te (DPE)

Date NED Procedure

~ ~~Re

Page 1

DESIGN REVIEW CHECK SHEET Plant Project File No.

Document Type Document No.

Revision

- iVA-l 5z

==

Description:==

Mark each item yes, no, or not applicable and initial each item checked by you.

1.

Were the inputs correctly selected and incorporated into design?

2.

Are assumptions used in the design adequately described and reasonable?

NOTE: Revie~ shall include but is not limited to applicable inputs specified in NED Procedure 3.1.A, paragraph 3.1.A.4.

3.

Are the appropriate quality and quality assurance requirements specified?

4.

Are applicable

codes, standards, and regulatory requirements including

~

~

issue and addendum properly identified, and are their requirements for design met?

5.

Has applicable construction and operating experience been considered?

6.

Have design interface requirements been satisfied?

7.

Was an appropriate design method used?

8. Is the output reasonable compared to inputs?

~cA o

9.

Are the specified parts, equipment, and processes suitable for the application?

10. Are the specified materials compatible with each other and the design environmental conditions to which the materials will be exposed?

wE0 proceaure 3.3/Rev.

59

DISCIPLINE DESICN VERIPICATION RECORD i.

Itmtrta:ticks to Verification Persornet Page 1

Plant AJP Project File Ko.

Oocmeot No.

Rev Level P4 Q (Ctass A)

( ) Seismic (Class 8)

( ]

FP-Q (Ctass 0)

( ) Other oesign verification shoutd be done in accordance Nith ANSl N45.2.)t, section 6, as amenoed by Regulatory Cuide 1.64, Rev. 2.

Special instructions:

Oiscipline Project Engineer

/

I(-

Verificaticn Oon~tation Appticability Oisci line Nechani ca l HVAC Electrical

)LC Other

()()()

Oisci line Civil Structural Seismic Equip. Qual.

Civil Stress Fire Protection Environnentat Qualification HLIaan Factors Hateriats

()()

(

)()()()()()()

Verification Nethods Used:

Oesign Revie~

( ) Alternate Calculations

( ) Qualification Testing

<es g Ackrxwtedgeaent of Ve ---'

(OPE)

No ( ). cannents attached.

Oate

'I 2.V/~Z (II. Resotuticn of Ccmaentst Ccaments Resolved (See Attached):

(RE)

~

Acticn taken nekes Oesign Oocunents Acceptable:

Oesign Verifier Oate Oate (OPE)

Oate NEO procedure 3 3IRe eo

~

h

~

I <<I

)

I ~

J t ~

~

r~

~t

/

P

~

I I

~

r

/I P,<~J k

I

(

i P )

r I '

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Page 1

DISCIPLINE TECHNICAL REVIEW of the COMPLETED DESIGN PACKAGE Plant Project File Ho.

Document Ho.

7= -4 7

Ir rl Rev Q

Level

[~ (Class A)

[ ) Seismic (Class 8)

[ ]

FP-Q (Class 0)

[ ) Other Initial each Discipline or Area of expertise addressed by this Discipline Technical Review of the Carrpieted Design package and forward completed sheet to the Lend Engineer.

Related discipline reviews may be combined on one sheet.

Appl icable Applicable Yes Ho Initial Disci line Yes Ho Initial Disci line Mechanical HVAC Electrical IKC Other

[) []

[) [)

[) []

[) []

Civil Structural Seismic Equip. Qual.

Civil Stress Fire Protection Enviroreental Qualification Human Factors Materials

[! (!

[) [)[)[)

(! (!

[) [)

t! [![)

Mark each item yes, no, or not applicable and initial each item checked by you.

1. 'ave design docunents or input free your discipline been properly interpreted and/or incorporated by other discipline?

Does the completed design package indicate that the transfer of design information within your discipline has been accurate, complete and proper?

3.

Are the installation instructions consistent with the intent of design docunents or input fram your discipline?

4.

Are the installation instructions within the coapleted design package adequate and correct?

Are procedures in place to cover installation if step by step instructions were not provided?

Are supporting disciplines or areas of expertise appropriately marked abave?

Is there consistency between drawings?

Indicate additional reviews required.

For each question on the check list not ans~ered

yes, explain on page 2.

If Hot Applicable,'ive reason.

Initial those disciplines reviewed.

Complete Design Package Accent!!hie/ Ye/ lgp+o [

Discipline Tech Reviewer Acknowledgement of DiscipljqIr lecnnlc?a....movie~

(DPE) lr

] - cottrnents attached.

Date Resolution of Comnentst Caaments Resolved (See Attached):

(RE)

Action taken makes Design Docunents Acceptaolet Discipline Tech Reviewer Date Date (OPE)

Date Proc.

3.3 Rev.

40

Page -1 DISCIPLINE TECHNICAL REVIEW of the COMPLETED DESIGN PACKAGE Plant Project File No.

Docunent No.

Rev Q

Level

[~ (Class A)

[ ) Seismic (Class 8)

[ ), FP-Q (Class D)

[ ) Other Initial each Discipline or Area of expertise addressed by this Discipline Technical Review of the Completed Design Package and forward completed sheet to the Lead Engineer.

Related discipline reviews may be combined on one sheet.

Applicable Applicable Yes No Initial Disci line Yes No Initial Disci line Mechanical HVAC Electrical INC Other

[)

[) ()

[) [)[),

Civil Structural Seismic Equip. Qual.

Civil Stress Fire Protection Envirorax.ntal Qualification Hunan Factors Materials

[) [)

[) [)

[) [)

[) [)

[) [)

[) [)

[) [)

6.

Mark each item yes, no, or not applicable and initial each item checked by you.

1. 'ave design docunents or input from your discipline been properly interpreted and/or incorporated by other discipline?

Does the conpieted design package indicate that the transfer of design information within your discipline has been accvrate, conplete and proper?

3.

Are the installation instructions consistent with the intent of design docunents or input from your discipline?

Are the installation instructions within the conpleted design package adeqvate and correct?

Are procedvres in place to cover installation if step by step instrvctions were not provided?

Are supporting disciplines or areas of expertise appropriately marked above?

7.

Is there consistency between drawings?

Indicate additional reviews required.

For each question on the check list not answered

yes, explain on page 2.

If 'Not Appl those disciplines reviewed.

icable, give reason.

Initial Complete Design Discipline Tech Acknowledgem~e t Package Acceptable~

Yes, M No [ ). - ctxnnents attached.

.M r p'ev'I ewe Date of Dlsciptsne %nn>~

Pgv~ wt Date

- 2S-Resolution of Coamentst Comnents Resolved (See Attached):

(RE)

Action taken makes Design Oocunents Acceptaole:

Discipline Tech Reviewer Date Date (DPE)

Date Proc.

3.3 Rev.

40

Page 1

DISCIPLINE TEC][NICAL REVIEW of the COMPLETED DESIGN PACKAGE Plant Project File Ho.

Document Ho.

/ I sl Rev Q

Level

'[WQ (Class A)

[ ) Seismic (Class 6]

[ )

FP-Q (Class 0)

[ ) Other Initial each Discipline or Area of expertise addressed by Package and forward conpleted sheet to the I.ead Engineer.

Applicable Yes Ho Initial Disci line Disci line this Discipline Technical Review of the Completed Design Related discipline reviews may be ccebined on one sheet.

Applicable Yes Ho Initial Mechanical HVAC Electrical IKC Other

[ )

[) []

[) [)

[) []

Civil Structural Seismic Equip. Qual.

Civil Stress Fire Protection Envirormenta[ Qualification Hunan Factors Haterials

[] [)

[)[] [)

[) [)

JA []

( I

[) [)

[ ]

icable,'ive reason.

Initial Mark each item yes, no, or not applicable and initial each item checked by you.

1. 'ave design docunents or input from your discipline been properly interpreted and/or incorporated by other discipline?

Does the coapleted design package indicate that the transfer of design information within your discipline has been accurate, complete and proper?

3.

Are the installation instructions consistent with the intent of design docunents or input from your discipline7 Are the installation instructions within the completed design package adequate and correct?

Are procedures in place to cover installation if step by step instructions were not provided?

6.

Are supporting disciplines or areas of expertise appropriately marked above?

7.

Is there consistency between drawings?

Indicate additional reviews required.

For each question on the check list not answered

yes, explain on page 2.

If, 'Hot Appl those disciplines reviewed.

Ccaplete Design Package Acc'-<l.~] eyrie g Ho [ ] - coenents attached.

Discipline Tech Reviewer Date Acknowledgement of Discipline Technical Review:

(OPE)

Date Resolution of Comnentst Cements Resolved (See Attached):

(RE)

Action taken makes Design Ooctxnents Acceptaole:

Discipline 'Tech Reviewer Date Date (DPE]

Date Proc.

3.3 Rev.

40

DISCIPLINE TECHNICAL REVIEM CCHHEHT SHEET Page 2

Plant Project File Ho.

Document Ho.

This sheet is only required when cccments are being made.

Conment Ho.

Corrment Resolution Resolved Initial/gate dc u 64 Lc LC Proc.

3.3 Rev.

40

Page 1

DISCIPLINE TECHNICAL REVIEW of the COMPLETED DESIGN PACKAGE Plant Pro)eat File Ho.

Document Ho.

Rev 8

Q Level

[WQ (Class A)

[ ) Seismic (Class 8)

[ )

FP.Q (Class O)

[ ) Other this Discipline Technical Revie~ of the Conp[eted Design Related discipline reviews may be combined on one sheet.

Applicable Yes Ho Init'nitial each Discipline or Area of expertise addressed by package and forward co))pleted sheet to the Lead Engineer.

Applicable Yes uo Initial Disci line Disci line C>v> l Structural Seismic Equip. Qual.

Civil Stress Fire Protection Environnenta[ Qualification Hunan Factors Materials Mechanical HVAC E lee tr ice l ISC

[)

W) 4))

)V')

[)

)~~

l) l) i 5.

6.

Date Other Mark each item yes, no, or not applicable and initial each item checked by you.

1. 'ave design docunents or input from your discipline been properly interpreted and/or incorporated by other discipline?

gag Does the ceryleted design package indicate that the transfer of design information within your discipline has been accurate, coop[etc and proper?

3.

Are the installation instructions consistent with the intent of design docunents or input from your discipline?

4.

Are the installation instructions within the completed design package adequate and correct?

Are procedures in place to cover installation if step by step instructions were not provided?

~fC

're supporting disciplines or areas of expertise appropriately marked above?

~65 Is there consistency between drawings?

Indicate additional reviews required.

For each question on the check list not answered yes, explain on page 2.

If Hot Applicable,'ive reason.

Initial those disciplines reviewed.

Complete Design Package A ~gab~ "-; +..

Ho

. )

- comnents attached.

Dlsolpline )eeh Revfevee Z.S'r 2

Aehnovledp)fppp. of Dfsoiplf)lp~ e

~

evl)ev:

lDPE)

Resolution of Ccnmentst Coaments Resolved (See Attached):

(RE)

Action taken makes Design Documents Acceptaole:

Discipline Tech Reviewer Date Date PE)

Date Proc.

3.3 Rev.

40

DISCIPLINE TECHMICAL REVIEM COMMENT SHEET Page 2

Plant Project File Mo.

Docunent Mo.

This sheet is only required shen caments are being made.

Comnent Mo.

Qv ESTIOiJ MoT h PLlcA L Conment T 0' Resolution Resolved Initial/Date RS;

-ALLA 4

j Pl% MT PR.OCE'OUP.E5,.

Proc.

3.3 Rev.

40

Page'1 DISCIPLINE TECHNICAL REVIEW of the COMPLETED DESIGN PACKAGE Plant Project File No.

Docunent No.

I <

C4-4'6 +V Rev Q

Level

[~ (Class A)

[ )

Se>sm>c (Class 8)

[ ]

FP Q (Class 0)

[ ) Other Initial each Discipline or Area of expertise addressed by Package and forward conpleted sheet to the Lead Engineer.

Applicable Yes No Initial Disci line Disci line this Discipline Technical Review of the Conpieted Design Related discipline reviews may be combined on one sheet.

Appl icable Yes No Initial Mechanical HVAC Electrical 18C

(

()/

t+l Vd Civil Structural Seismic Equip. Qual.

Civil Stress Fire Protection Envirormental Qualification Hunan Factors Materials

'etpiete Design Package Ac,~tablet Yes [.~

No 4 - conments attached.

~

n

~ I Discipline tech Reviewer Date Acknowl "~~ Disclplte4c ~""~ col R>>'-<<:

(DPE)

Date Other

[) [)

Mark each item yes, no, or not applicable and initial each item checked by you.

1. 'ave design docunents or input from your discipline been properly interpreted and/or incorporated by other discipline?

Does the coapieted design package indicate that the transfer of design information within your discipline has been accurate, cccpiete and proper?

Are the installation instructions consistent with the intent of design docunents or input frcm your discipline?

Are the installation instructions within the coapleted design package adequate and correct?

5.

Are procedures in place to cover installation if step by step instructions were not provided?

6.

Are supporting disciplines or areas of expertise appropriately marked above?

c" 7.

Is there consistency between drawings?

Indicate additional reviews required.

For each question on the check list not answered

yes, explain on page 2.

If 'Not Applicable,'ive reason.

Initial those disciplines reviewed.

Resolution of Comnentst Ccm"..~tRes(lived gee A(tac~).

~

(RE)

Action t~en makes.'..~cmggts Acceataol~

Discipline Tech Review ;

Date Date I

9+

<OPE)

Date Proc.

3.3 Rev.

40

0 ISCIPLINE TECHNICAL REVIEM CCHHEHT SHEET Page 2

Plant Project File No.

Document No.

-'4 Rev This sheet is only required uhen contents are being made.

Conment No.

Conment QE,s~~+ xm4cT wainmhzq

&AoI;I.o~<

- z 0

r SE,C~oAI S>PeCZEcc ~IITheji~ /RENT 3 f SRoOLO RV

+I'-AAlhM~ BQsII. I HK QOS~ !-or AVE.

nm 6E. ~

Resolution 1)~

~fMS5ED IO QEFLKC+

4)g5 Q~fAf.O "to Resolved Initial/Date Proc.

3.3 Rev.

40

le g

age~ of NED INTERDISCIPLINE REVIEW REQUEST (IRR)

To:

From:

IRR g'OD/RET/PCR/PCN g:

Unit/Subunit Unit/Subunit Plane ~NP Details of Review Request:DUE TO RECENT CONCERNS ASSOCIATED WITH CSIP ALTERNATE MINI-FLOW SYSTEM INTEGRITY, MODIFICATIONS TO THE OPERATING LOGIC OF VALVE 2CS-V575SA-1 AND 2CS-V759SB-1 ARE NECESSARY.

THESE MODIFICATIONS INCLUDE THE ADDITION OF A RCS PRESSURE PERMISSIVE IN SERIES WITH A SAFETY INJECTION SIGNAL.

TWO NEW 2/C FIELD CABLES ARE REQUIRED AS FOLLOWS:

CABLE 317N-SA FROM PIC-1 TO SSPS (A) OUTPUT BAY 2 AND CABLE 319N-SB FROM PIC-4 TO SSPS (B) OUTPUT BAY 2. ADDITIONALLY, EXISTING FIELD CABLES 317F SA AND 319F SB WILL BE RE-ROUTED TO OUTPUT BAY 2 OF THE SSPS CABINETS.

PROVIDE THE NECESSARY ELECTRICAL DESIGN INPUT TO SUPPORT THIS MODIFICATION. PLEASE PROVIDE A SAFETY EVALUATION, ELECTRICAL DESIGN IMPACT STATEMENTS, AND DESIGN VERIFICATION RECORDS.

OBTAIN THE NECESSARY CIVIL, ELECTRICAL ALYSIS, AND APP.

R INTERDISCIPLINARY DESIGN SUPPORT.

4

Response

Required By:

Authorized Man-hours MAPS Project No.:

Responsible Supervisor/Date:

Charge Number Phase:

Activity:

&4M e 'ZL/

is RVIgvaZ~ see A><~&5 7>>< '>>~

I k)

(OOQ ~i~.

CDPhSW f)5geaaE7f M.6 l'5 hl01

~<5 P~ g~<<~(5 QPP%~+fPC~

MWJ(WD +DR SSW.

Information Design Verified:

Attachments (list):

Yea No

~

pY~

/J')

g>e~ ff 'N'I'l

~/8/ i j >

ply c-> c'~

Responsible Supervisor/Date Actual Man-hours expended 0

Page 6

Rev.

4

I File g Page~ of~

NED INTERDISCIPLINE REVIEW REQUEST (IRR)

To:

From..

Details of Review Request:

IRRt'lt'.

MOD/RET/PCR/PCNP Unit/Subunit Unit/Subunit PlantQQQ'HIS MODIFICATION WILL INVOLVE TEMPORARY REMOVAL OF SAFETY INJECTION PIPING FROM PENETRATIONS P415,

P418, AND P426 WHILE INSTALLING STRAINERS.

/Z4.+ + 4, ~~7 PLEASE PROVIDE DESIGN INFORMATION.

RUSHtttt

Response

Required By:

Authorized Manhours Phase:

Activity:

Response/Justif icati on 5Zt

~@ACR gO gg+6V p @AC Q g p B~ ~R ]'k)+Q~IOQ 7'e" cF 7H+ /eSTAc-C~r/orJ QMAqg. VHK Sae~ckl eggs vp'F'C.lE'v llv 7 Q/5 +g g ggpp~gg~c ~ ~gg gag~++

/M Z R/Z.Q8

&Z8 l~

P/ft('g +~g~

Attachments (list):

Responsible Supervisor/Dat

= " '

Distribution:

Actual Man-hours expended NED GuidelineNo.

E-24 Revision 3 (6/90)

gW '~p

ile P

age~ of ClV)LUNT 1 ~ f953 To:

From:

NED PLINE REVIEW REQU IRR y.

MOD/RET/PCR/PCN 0:

Unit/Subunit Unit/Subunit Plant ~p~

u -I Details of Review Request:AS PART OF PCR-6547, P&B MDR-+

ROTARY RELAYS ARE BEING ADDED TO THE SOLID STATE PROTECTION SYSTEM OUTPUT 2 BAYS, TRAIN "A" AND "B". PLEASE PROVIDE THE NECESSARY STRUCTURAL EVALUATION AND CIVIL MOUNTING DETAILS FOR THE ADDITION OF THE K711 RELAYS. IF NECESSARY REFER TO PCR-5045 WHICH PERFORMED A SIMILAR MODIFICATION DURING RFO 03.

Authorized Man-hours MAPS Project No.:

Response/Justification:

4 Responsible Supervisor/Date:

~~

Charge Number Phase:

Activity:

Information Design Verified:

Attachments (list):

Yes No Responsible Supervisor/Date ~

Distribution:

Actual Man-hours expended

/

-i~: H<C-wax->e-A q

d( +sgcg~~<<

Page 6

Rev.

4

RESPONSE

TO IRR HI-624 The potter

& Brumfield MDR-4103-1 relays are seismically qualified for installation in the output bay two compartment of the SSPS cabinets.

The installation of the relays in each output bay two compartment will not affect the seismic qualification or functional capabilities of the SSPS cabinets, reference calculation HNP-C/EQ-1089.

The relays shall be installed in location K711 in both output bay two compartments.

The relays shall be mounted with g6-32 x 3/8" long min. (or use g6-32 x 1/2" long), slotted pan head machine screws with helical spring lock washers.

The machine screws shall be snug tight.

The machine screvs shall be carbon steel, zinc plated and shall be in accordance with ANSI B18.6.3.

The lock washers shall be carbon steel and in accordance with ANSI B18.21.1.

Refer to Calculation HNP-C/EQ-1089 (PCR 5045) for the structural analysis for identical P&B relays mounted in locations K719 through K723 in both output bay two compartments.

The machine screvs for these particular relays vere originally g6-32 x 1/2" long and later were revised to be g6-32 x 3/8" long; per PCR 5045, Field Rev.

17.

0 leg Page~ of~

NED INTERDISCIPLINE REVIEW REQUEST (IRR)

To:

From:

Details of Review Request:

IRRg:

MOD/RET/PCR/PCNP Unit/Subunit Unit/Subunit P

lant+Qg'NP(PCR-6547)

WILL INSTALL A NEAR DUPLICATE OF THE MINI-FLOW ORIFICE STRAINER THAT WAS INSTALLED AT RNP.

WE REQUEST THAT JIM RE-RUN HIS MATHCAD MODEL FOR HARRIS SPECIFICS.

THE SPECIFICS ARE MARKED UP IN THE RNP CALC.

(RNP-M/MECH-1468).

NEW CALC.

NUMBER IS SI-0044.

Response

Required By:

Authorized Manhours Phase:

Activity:

'Viz/>

sponse/Justification:

4&o Aaa, l Wg c

7. /Z C.

04 s' ~

0 ~ c Fc ca+ o ~ ~

(eF4 t-(~4 L a<<~~c t-e F'~e Attachments (li t):

Responsible Supervisor/Da e

Distribution:

Ccd cu l~ o~,

XF Is renig s i~ - oFF rs r'~~A'e~ aZ()

c a4 ~p~~,

CdG ~

lg c if/ U a(p aG

~

Actual Man-hours expended NED GuidelineNo.

E-24 Revision 3 (6/90)

ile 4 Page~ ng~

NED INTERDISCIPLINE REVIEW REQUEST (IRR) go~ ~l<~

J

)ib To From:

IRRg:

MOD/RET/PCR/PCN8 eau Unit/Subunit Unxt/Subunit Plant~

Details of Review Request:

PLEASE PROVIDE PIPING DESIGN SUPPORT FOR REFERENCED MODIFICATION. SCOPE AS DISCUSSED.

-9-ll=u-Responsible Supervisor/Date Phase:

Activity:

>++~>~~ zP < P~@>~y)8.. >Pig~~ A<i) s.

j~p Pgwl IP'S~ /+

+~ A<p'cAeP'~

g Attachments (list):

Responsible Supervisor/Dat Distribution:

7~ Actual Man-hours expended ~f

'Y NED GuidelineNo.

E-24 Revision 3 (6/90)

" 7 Page~ of~

To:

From:

~p/'/ j NED INTERDISCIPLINE REVIEW REQUEST (IRR) e (g97 I

IRRjj'.

MOD/RRT/PCR/PCNP Plant~

Unit/Subunit Unit/Subunit Details of Review Request:

PLEASE PROVIDE I&C SUPPORT FOR PCR 6530.

esponse/Justification:

Responsible Supervisor/Date Charge Number Phase:

Activity:

<////s~

/ ZHHPE CDJ8 7A'K&r7JF AErQ K~C r uiKiM/aCi)

C/'uSPp'WW/'6W

/A Wur ~M~M~~Hf~ -uaCo&~H ~-W-V'7 Attachments (list):

Responsible Supervisor/Date..

Distribution:

Actual Man-hours expended NED GuidelineNo.

E-24 Revision 3 (6/90)

page~ of~

NED INTERDISCIPLINE REVIEW REQUEST (IRR)

Cp

-o~ u~ S<lo)

To:

Frot.

MOD/RET/PCR/PCNg Unit/Subunit Unit/Subunit Plant HNP Details oX Review Request:

CHARGING/SAFETY INJECTION ALTERNATE MINI-FLOW RELIEF VALVES 2CS-R557SN-l 6 2CS-R558SN.l ARE BEING REMOVED PER THIS PCR.

PLEASE PROVIDE MEQ DOCUMENTATION FOR THIS DESIGN CHANGE.

Response

Required By:

Authorized Manhours aoaa Phase:

DESIGN Activity:

sponse/Justification: -'4 5 Attachments (list):

Responsible Supervisor/Date Distribution:

ctual Man-hours expended B 4~'bh NED GuidelineNo.

E-24 Revision 3 (6/90)

RESPONSE

TO ZRR-HM-1252 The information you provided was reviewed for impact on the MEQ program. All proposed MEQ documentation revisions are attached.

The following MEQ documents must be revised upon closeout of the applicable Pt'R, and therefore must be listed in the PCR as "Design Documents Requiring Revision".

2166-S-2530, MLA 2166-S-2530, MLB 2166-S-2530, 0111 VENDOR MANUAL, VM-BJS E

DESIGN IMPACT:

From an EQ perspective there is no adverse impact resulting from the proposed valve deletions.

The response to this IRR is a "Documentation Change" only.

Page of

~ ) ~ ~ J

~

~ ~

~

g iJihad grot NED INTERDISCIPLINE REVIEW REQUEST (IRR)

To.

From IRR8:

MOD/RET/PCR/PCNP Unit/Subunit Unit/Subunit Plant HNP Details of Review Request:

SAFETY INJECTION PIPING IS BEING MODIFIED AS SHOWN ON PIPING DRAWING SUBMITTED 9.11-92.

PLEASE PROVIDE STRESS/HANGER DOCUMENTATION.

Response

Required.By:

Authorised Manhours kJIL32 Phase:

Activity:

esponse/Justification:

QcQsmMRTzr u PM'pC. S itx56 AQRAs 6 '5 Ptuo SQpcoM QE&T.66 Lo'a~'ll AAu& Bv.~ R.V-fo~csli LAc- ~Q<got.f Qddsu Loath LQR&1La~~

Co 'AEc6IBvi'L.Swivet< 4a Qk 'lL Qo%a SnpRf Sv'fvcc Q~s (0+%9@- HoR,,-WQu,-dew A~a-R4)b) E4~~ G..x.e 5am~<3AL-l 4nl91-2.

A~un MA ill AMMttM& tvocfa ARU& ~LMKQ Qm AC Af.ftc<M Q~wf uc 5Hmt's

~~m Cuc. Q~6 t A~K,. s&f &i~S4ua~6 hfdf ct&

>AE ELGl~Ku of-

'h.Cs. XC..Ch Auo 5'0'octa La~. i%f Cm inc. VEQ~n&f&5& b.a'.3X,.tn hcvsnM 'fAK A~ctb Arx

~tauon Xe ~cna~ ~~ ~cc. ~-,auo~u Q~crn~~> <Atra. A~ hie. ~~~ ~~~us.

Plz aC gufbChhaTa.u 5AAU BG ~OKLA QPbtl MM.waLrt'%LLAMA LbtnC'~t~Q.

Attachments (list):

CQ~

CH2.

Abc.

~w6~%5 A6 CQf ~~a XwcAcT 9

~Ag~~ JQJALQAg~& foe'UtfLlhiibAuo 842lSM<'esponsible Supervisor/Dat lctual Man-hours expended Distribution:

NED GuidelineNo.

E-24 Revision 3 (6/90)

ile g

/'iIL1Il NED INTERDISCIPLINE REVIEW REQUEST (IRR) p >(6 IRRg:

MOD/RET/PCR/PCN8'lant HNP To:

From:

E Details of Review Request:

Unit/Subunit Unit/Subunit PLEASE DETERMINE WHETHER OVER-PRESSURIZATION OF A SMALL PORTION OF THE SI SYSTEM BY APPROXIMATELY 2Q / -EXCEEDS ALLOWABLE STRESS.

LINE NUMBERS ARE 2CS2-785SN-1, 2CS2-784SN-l, 2CS2-783SN-l, AND 2CS2-786SN-1>

WITH ASSOCIATED VENTS Ec DRAINS. DESIGN PRESSURE IS 2735 PSIG @300oF.

WHILE TEST CONDITIONS HAVE REACHED 2800PSIG 9 APPROX.

100oF.

A<<<<~~~~

p c.s 2 -ad sM-f g egg- +975~-/

8 c5 W

+~

S~-I vlivlrz Phase:

Activity:

esponse/Justification:

QE. cKKcv VG&eci. Qf '%oh Q~ 4s, %KMX~ow ~v QK 0mocMMs cvc QC.Q.-45%"i (XB-Am-S~SQ Auc a AueCAu Attachments (list):

Responsible

~

Supervisor/Dat.

)~jQ'L Distribution:

Actual Man-hours expended f-2) ~(Z.

NED GuidelineNo.

E-24 Revision 3 (6/90)

File f age 1

of 33 NC.

ATTACH.

CPIIL UNlT

,c93 NED INTERDISCZPLINE REVIEW RE{}UEST (IRR)

Too Froi'is form is used to rov ae IRR g:

HC-169 MOD/RET/PCR/PCN g:

6547

%t/Subunit SS CIV

-SU ORTS unit/Subunit SS C V

-S SS nterd sc i e review docume tat o

Plant HNP Details of Review Request:

REFERENCE - PCR-6547, DELETION OF RELIEF VALVES AND ADDZTION OF ORIFICES AND STRAINERS ATTACHED ARE THE SIGNED OFF SUPPORT LOAD SHEETS FOR PCR-6547 AS WE KNOW IT AS OF 12:00 P.M.

ON SEPTEMBER 25,1992.

PLEASE USE THESE LOADS IN YOUR SUPPORT DESIGNS AND EVALUATIONS FOR THE ABOVE MENTIONED PCR.

THESE LOADS ARE AS GOOD AS THE INFORMATION USED TO DEVELOP THEM SINCE NO APPROVED DRAWINGS HAVE BEEN RECEIVED AS OF THIS WRITING.

IF THERE ARE ANY QUESTIONS PLEASE CONTACT JOHN HOPKINS AT X-6734.

esponse Required By:

Authorized Man-hours MAPS Project No.:

PCR-6547 Responsible Supervisor/Date Charge Number Phase:

Activity:

Response/Justification:

Attachments (list):

Responsible Supervisor/Date Actual Man-hours expended Distribution:

NED Guideline No. E-24 Revision 4

(E666/rlj

CAROLINA POWER

& LIGHT COXP7LMY PLAHT HARRIS NUCLEAR PLANT CALCULATIONNUMBER 14 1-lA PCN/PID NUMBER PCR-6547 PAOE REVISION SUBIECT SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

0INATOR'S INITIALS/DATE c.J

'S D/ITIALS/DATE HANGER NO.CS- -

2 NODE PT.7 ISO NO.

6-8 SUPPORT SYSTEM CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD

& TAD DBE SAM OBE(Inertia DBE(Inertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

THERMAL I F,

(LBS )

2 ~

-132.

44.

70.

x (in)

0. 00 Fy (LBS)

-217.

57.

124.

176.

DISPLACEMENTS Y

(in) 0.00 F~

(LBS) 5 (in) 0.0111 Ng (FT-LBS) l4I/

(FT-LBS)

(FT-LBS)

THERMAL ZZ

<ACCIDEÃD THERMAL ZZZ posf-Acc!DBIn NOTES: 1.

+X ~ NORTH,

+Y ~ UP,

+5 ~ EAST.

2 ~

3 ~

CAROLINA POWER fi LIGHT COMPANY P

LANI'ARRIS NUCLEAR PLANT CALCULATIONNUMBER 141-1A PCN/P JD NUMBER PCR-6547 PAOE REVLSION SlJBJECI'I CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

OklQINATOR'SMTlALS/DATE 9 7P-a~

HANGER NO.C 7

ISO NO.

-68 SUPPORT SYSTEN CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD 6i TAD DBE SAM OBE Inertia)

DBE(Inertia)

UPSET (+)

UPSET (-

EMERGENCY(+)

EMERGENCY(

)

THERMAL I Fx (LBS)

-39.

-42.

76.

122

'OS 0.00 Fy (LBS)

DISPLACEMENTS Y

(in) 0.0098 (LBS) 5 (in)

-0.0475 (FT-LBS) le (FT LBS)

(FT-LBS)

THERMAL II (AccIDEÃn THERMAL III

/)0$f.ACCIDQG)

NOTES! 1.

+X > NORTH)

+Y ~ UP,

+5 < EAST

CAROLINA POWER R LIGHT COHPANY I'LANT HARRIS NUCLEAR PLANT CALCULATIONNUMBER 141-1A PCNJPID NUMBER PCR-6547 RAOB REVISION SUBJECT SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

ORJOINATOR'S INITIALS/DATE CHP~BI'S INITIALTB

~tel '1~~

HANGER NO.CS-H-4233 ISO NO.

A-236-CS-58 SUPPORT SYSTEM CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD 6 TAD DBE SAM OBE(Inertia DBE(Inertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

THERMAL I (NOLMAU THERMAL II r,

(LBS) 44

'32.

38.

61.

x (in) 0.00 Fv (LBS)

-384.

-82

'95.

289.

LnL)1.

l55 DISPLACENENTS Y

(in) 0.00 r,

(LBS)

S (in)

-0.0520 Ng (FT-LBS)

Ny (FT-LBS)

Nz (FT-LBS)

THERMAL III NOTES:

1.

+X a NORTH)

+Y > UP(

+Z a EAST.

2.

3.

CAROLINA POWER fi LIGHT COHPldpg PLANT HARRIS NUCLEAR PLANT CALCULATIONNVMBBR 141-1A PCN/PtD NVMBBR PCR-6547 PAOB RBV!SION SVBlECT SI CHARGING PUMP ALTERNATE MINI-FLOW LINE/ RELIEF VALVES REMOVED/

FLOW ORIFICES AND STRAINERS ADDED

=

WITH LEAD BLANKETS.

ORIGINATOR'S MTlALS/DATE CHPXK1~JI'S INlTIALS/DATE m)~( 11(l HANGER NO.CS-H-42 5

NODE PT.7163 ISO NO. CS 58 SUPPORT SYSTEN CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD 6 TAD DBE SAM OBE (Inertia)

DBE(Inertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

THERMAL I II(DAEDAL)

THERMAL II (ACCIDENT)

THERMAL III posT Acc(DQfn (LBS) 0.0275 Pv (LBS)

-166.

99.

166.

DISPLACENENTS Y

(ia) 0.00 (LBS) 5 (in)

-0.0723 (PT-LBS)

Ny (PT LBS)

Mz (PT-LBS)

NOTES: lo

+X > NORTH'Y ~ UP(

+Z > EAST+

2 ~

3 ~

CAROLINA PO%ER fi LIGHT COMPANY HARRIS NUCLEAR PLANT CALCULAI1ON NJMBBR 141-1A PCR-6547 JAae RB'/LSIOH SUBJBCT SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

ORJOlNATOR'S MTIALS/DATB 9-z3~z CHBCKBR'S DIJTIALS/DATB a/-.

I HANGER NO.C - -4 68 NODE PT.7 ISO NO.

- S-58 SUPPORT SYSTEX CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL IIZ PAD

& TAD DBE SAM OBE(Inertia)

DBE ( Inertia)

UPSET

(+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

THERMAL I (HOkllAU THERMAL ZZ

<ACClDEVfl THERMAL III rx (LBS) 2 1 ~

2 ~

89.

144.

KLc'l x

(ia) 0.00 r

(LBS)

DZSPLACEMENTS Y

(ia) 0.0152 r,

(LBS)

-104

'27

~

75

'29.

S (ia) 0 F 00 Nx (rT-LBS)

(rT-LBS)

(rT-LBS)

NOTES'

+X NORTH(

+Y ~ UPs

+Z EAST 2 ~

3.

CAROLINA POWER fi LIGHT COMPANY HARRIS NUCLEAR PLANT CALCULATIONNUMBER 14 1-1A PCR-6547 PAOE REVISION SUBJECf SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED)

FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

ORIGINATOR'S INfflALS/DATE 3("i 9-z3-;z CHECKER'S MTIALS/DATE HANGER NO.C -H-ISO NO.

-C -5 SUPPORT SYSTEN CONDITION DEADWEIGHT THERMAL I THERMAL IZ THERMAL III PAD

& TAD DBE SAM OBE (Inertia)

DBE(Znertia)

UPSET (+)

UPSET

-)

EMERGENCY(+)

EMERGENCY(-)

THERMAL I (NOkMAL)

THERMAL IZ (ACCQKNn THERMAL IZZ

()OSr ACC(na(TI r,

(LBS)

X (in) 0.00 (LBS)

-262.

80.

108.

187.

DISPLACEMENTS Y

(in) 0.00 r,

(LBS) 63.

-213.

35.

56.

Z.OLn 5

(in) 0.00 le (rT-LBS)

Ny (rT-LBS)

(PT-LBS)

NOTES 1

+X + NORTH)

+Y + UP )

+2

+ EAST 2.

3 ~

CAROLINA POKER fi LIGHT COXPANY PIAHT HARRIS NUCLEAR PLANT PCR-6547 PAOB 141-1A REVISION SUBJECT SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

ORIGINATOR'S INTTIALS/DATE gr',

CHECKER'S INITIALS/DATE HANGER NO.CS- -4 7

ISO NO.

36-S-58 SUPPORT SYSTEM CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD 6 TAD DBE SAM OBE(Inertia)

DBE(Inertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

r, (LBS)

Fy (LBS)

-81.

12

'5.

60.

F, (LBS)

-4.

-17 ~

22

'6.

Ng (FT-LBS)

(FT-LBS)

(FT-LBS)

THERMAL I (HORllAU THERMAL II (ACCIDEÃl)

THERMAL III POST.ACCIDBÃn X

(in) 0.0324 DISPIJlCI94l3lTS Y

(in) 0.00 5

(ia) 0.00 NOTES: 1.

+X ~ NORTH(

+Y < UP(

+5

< EAST.

2.

CAROLINA POKER

& LIGHT COMPANY HARRIS NUCLEAR PLANT CALCULATIONNUMBER 141-1A PCN/PID NUMBER PCR-6547 PAGE REVISION SUBJECT SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

ORIOINATOR'S INITIALS/DATE C

-z -a" CHECKER'S INITIALS/DATE H//M/8 I HANGER NO.CS-

29 ISO NO.

6-S-58 SUPPORT SYSTEN CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD

& TAD.

DBE SAM OBE(Inertia)

DBE(Znertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

THERMAL I

/MORNAY THERMAL IZ "

Fx (LBS) 0.0572 Fy (LBS)

-65.

10.

76.

116.

DISPLACENENTS Y

(in) 0.00 F~

(LBS)

-4.

112.

89.

132.

0.00 Nz (FT LBS)

Ny (FT-LBS)

(FT-LBS)

THERMAL III POST.ACCIDENT)

NOTES: 1.

+X

NORTH,

+Y UP,

+2 EAST.

2 ~

3 ~

CAROLINA POSER fc LIQHT COMPANY HARRIS NUCLEAR PLANT CALCULATIONNUMBER 141-1A PCR-6547 PAOE REVISION SUBJECT SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

ORIOINATOR'S INmALS/DATE q.z~-a=

CHECKER'S INITI/QS/DATE s (>-s]S ~

HANGER NO.

- -4 ISO NO.

SUPPORT SYSTEX CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD

& TAD DBE SAM OBE(Inertia)

DBE ( Inertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

Px (LBS)

-9.

-34.

442.

657.

Fy (LBS )

r, (LBS)

)Ix (PT-LBS)

My (FT-LBS)

(FT-LBS)

THERMAL I tNOXl4ALI THERMAL ZZ (ACClDe(n THERMAL IZI 00$ T ACCQ)f&Q X

(in) 0.00 DISPLACENENTS (in) 0.0218 (in) 0.0244 NOTES:

1

+X > NORTH(

+Y ~ UP,

+Z < EAST.

2 ~

3 ~

C3EROLZNA POSER fc LIGHT COXPANY PLANT HARRIS NUCLEAR PLANT CALCUlATIONNUMBER 141-1A PCR-6547 PAOE REVISION SUBIECT SI CHARGING PUMP ALTERNATE MINI FLOW LINE( RELIEF VALVES REMOVED(

FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

ORIOINATOR'S INITIAL%DATE

('

I -Z~-'IZ.

CHECKPJI'S INITIALS(DATE P~. ~i.)3s~

HANGER NO.CS-H-4272 NODE PT.7760 ZSO NO.

A-236-CS-59 SUPPORT SYSTKN CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD

& TAD DBE SAM OBE Inertia)

DBE(Inertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

THERMAL I THERMAL ZZ IACClDEY!)

THERMAL IZZ Fx (LBS)

X (in) 0.0304 Fy (LBS )

DZSPLACEIQBITS Y

(in) 0.0044 Fg (LBS)

-15.

38.

85.

141.

(in) 0.00 (FT-LBS) lCy (FT-LBS)

( FT-LBS )

NOTESI 1 ~

+X > NORTH(

+Y < UP(

+2

> EAST 2 ~

3 ~

CAROLINA POWER fi LIGHT COMPANY PLANT HARRIS NUCLEAR PLANT CALCULATIONNUMBER 141-1A PCN/PID NUMBER PCR-6547 IAOE RE I/ISIOIo SUBIECf ING P~P ALTERNATE MINI-FLOW LINE RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

0RIOINATOR'S INITIALS/DATE c.Q 5->swz.

CHECKER'S INITIALS/DATE P~ ~~5~

HANGER NO.CS-

6 ISO NO.

SUPPORT SYSTEM CONDITION DEADWEIGHT THERMAL 2 THERMAL II THERMAL IZI PAD

& TAD DBE SAM OBE Inertia)

DBE(Inertia)

UPSET (+)

UPSET (-)

Fr (LBS)

Fy (LBS)

-344.

22 ~

134.

223.

F, (LBS)

Mg (FT-LBS)

My (FT-LBS)

M2 (FT-LBS)

EMERGENCY +)

EMERGENCY(-)

THERMAL I OIOlllAL)

THERMAL ZI IACCIDENT)

THERMAL III iMST.ACCIDEÃn (in) 0.0380 DZSPLACEMENTS Y

(in) 0.00 5

(in) 0.0135 NOTES: l. +X ~ NORTH,

+Y a UP,

+5

~ EAST.

2 ~

3.

CAROLZM7L POSER 6 LZGHT COMPANY PLAINT HARRIS NUCLEAR PLANT CALCULATIONNUMBER 14 1-1A PCR-6547 PAGE REVISIOH SUBJECT SI CHARGING PUMP ALTERNATE MINI-FLOW L'INE RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

0RIOINATOR'S INITIALS/DATE CHECKER'S INITIALS/DATE HANGER NO.CS-H-4243 NODE PT.7790 ISO NO.

-236-CS-59 SUPPORT SYSTEM CONDITION DEADWEIGHT THERMAL I THERMAL IZ THERMAL IIZ PAD 6 TAD DBE SAM OBE(Znertia)

DBE(Inertia)

UPSET (+)

UPSET (-)

Fx (LBS)

Fy (LBS)

-245.

7 ~

128.

223',

(LBS) 76.

-2 77

'16.

Ãz (FT-LBS) le (FT-LBS)

(FT-LBS)

EMERGENCY(+)

EMERGENCY(-)

THERMAL I (HOAMAl)

THERMAL II (ACCUSANT)

THERMAL IIZ POST ACCIDEÃQ x

(in) 0.0768 DISPLACEMENTS Y

(in) 0.00 5

(in) 0.00 NOTES: 1.

+X < NORTH,

+Y > UP/

+5 < EAST.

2 ~

3 ~

CAROLINA POWER fi LIGHT COMPANY PLANT HARRIS NUCLEAR PLANT CALCULATIONNUMBER 141-1A PCNIPJD NUMBER PCR-6547 PAOE REVLSION SlJBJECl'I CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

ORlOlNATOR'S JNTIALSIDATE 9,

'I-7~-eZ CHECKER'S JNJllALSIDATE P~. =l/<SPt HANGER NO.

7 ISO NO.

S-SUPPORT 8YSTEN CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD

& TAD DBE SAM OBE(Inertia)

DBE(Inertia)

FS (LBS)

Fy (LBS)

FB (LBS)

-68.

-40.

88.

143

'FT-LBS) l4y (FT-LBS)

(FT-LBS)

UPSET (+)

UPSET

-)

'EMERGENCY(+)

EMERGENCY(-)

THERMAL I INOIMAQ THERMAL II (ACCIDEYll THERMAL IZI posT.AccUKYn x

(in) 0.0797 DISPLACEMENTS Y

(in) 0.0085 0.00 NOTES: 1.

+X > NORTH(

+Y > UP(

+2

> EAST.

2 ~

3 ~

CAROLINA POWER Cc LIGHT COXPANY HARRIS NUCLEAR PLANT CA~+Ox NUMEEa 141-1A PCR-6547 PAGE REYlSIOH SVBJECI'I CHARGING PUMP ALTERNATE MINI-FLOW LINE) RELIEF VALVES REMOVED)

FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

OalalNA VOa S emu ~Am c4 CHPLl<ER'S MTIALS/DATE HANGER NO.CS-H-4261 ISO NO.

A-236-CS-59 SUPPORT SYSTEX CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD S TAD DBE SAM OBE Inertia DBE(Znertia)

UPSET (+)

UPSET

(

)

EMERGENCY(+)

EMERGENCY(-)

rx (LBS) r (LBS)

-186.

-4.

75 ~

126 rg (LBS)

Nz (rT-LBS)

Xy (rT LBs)

( rT-LBS)

THERMAL I THERMAL IZ (ACCDENT)

THERMAL IZZ POST.ACCDEÃE) x (in) 0.0923 DISPLACEMENTS Y

(in)

0. 00, (in)

-0.0261 NOTES: 1.

+X ~ NORTH,

+Y > UP)

+Z ~ EAST.

2 ~

3 ~

CAROLINA PO>ER

% LIGHT COMPANY PLANT HARRIS NUCLEAR PLANT PCR-6547 SUBJECT SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

CALCULATIONNUMBER 141-lA PAOB ORIOINATOR'S INIALS/DATB c.q g-">-'tz CHP~~JI'S INITIALS/DATB HANGER NO. S- -4 47 NODE PT.7840 ISO NO ~

6-SUPPORT SYSTEM CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL IIZ PAD

& TAD DBE SAM OBE(Inertia)

DBE(Inertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

THERMAL I (NORMA@

THERMAL ZZ (ACCIDEtC)

THERMAL ZIZ Pz (LBS)

X (in) 0.1368 Fv (LBS)

-94.

4 ~

52.

89.

DZSPLACEKENTS Y

(in) 0.00 r,

(LBS) 5 (in)

-0.0970 l4z (PT-LBS) llv (PT-LBS)

( PT-LBS

)

NOTES: l. +X > NORTH'Y < UP(

+Z a EAST.

2.

3 ~

CAROLINA POWER fa LIGHT COXPAgy PIAHT HARRIS NUCLEAR PLANT PCN/PID IIUMBER PCR-6547 PAGE 141-1A REYI$ION

$UBJECT SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

ORIGINATOR'$ INITIALS/DATE Ql CHECKER'$ INITIAL$/DATE I

I ~,C HANGER NO.CS-H-4 NODE PT.7 ISO NO.

6-S-59 SUPPORT SYSTEM CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL IZI PAD 6 TAD DBE SAM OBE(Znertia)

DBE (Inertia)

UPSET (+)

UPSET (-)

EMERGENCY +

EMERGENCY(-)

THERMAL I (HOkNAL)

THERMAL II rx (LBS) 0.1838 r

(LBS)

-68.

32.

56.

DZSPLACEMENTS Y

(in) 0.00 r,

(LBS)

-112.

24.

37 5

(in) 0.00 Nx (FT-LBS)

Ny (FT-LBS)

(FT-LBS)

THERMAL IIZ I)OST-ACCKIEI)TI NOTESI 1

+X ~ NORTH)

+Y ~ UP)

+5

~

EAST'.

3 ~

CAROLINA POWER

& LIGHT COMPANY IS NUCLEAR PLANT euZULATIOaWISER 141-1A PCNlPID NUMBER PCR-6547 PAOE REVISIOH SUBJECT iSI CHARGING PUMP ALTERNATE MINI FLOW LINE ~ RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

ORIODIATOR S MTIALSlDATE CHECKER'S MTIALS/DATE n)~~~

~

HANGER NO.

-4 66 NODE PT.7 ISO NO.

- S-5 SUPPORT SYSTEX CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL IIZ PAD

& TAD DBE SAM OBE(Inertia)

DBE(Inertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

THERMAL I OIOkMAQ THERMAL IZ (ACCIDEÃA THERMAL IZZ (TOST-ACCDENn Fx (LBS) 0.2109 Fy (LBS)

-49.

24.

41.

DISPLACEMIKTS Y

(in) 0.00 Fg (LBS) 5 (in)

-0.0751 Nx (FT-LBS) le (FT-LBS)

Nz

( FT-LBS )

NOTES:

1 ~

+X ~ NORTH,

+Y ~ UP,

+5 < EAST 2 ~

3 ~

CAROLINA POWER

& LIGHT CO)G'iQiY HARRIS NUCLEAR PLANT CA~TIONmmER-141-1A AN/PID NUMBER PCR-6547 PAOE REViSION SUBJECT CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

ORIOINATOR'S MTIALS/DATE q- >-~z CHECKER'S MTTALS/DATE HANGER NO.CS-

7

• RUOISO NO.

-C -5 SUPPORT SYSTEM CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD

& TAD DBE SAM OBE(Inertia)

DBE(Inertia)

Fg (LBS) 201.

12.

18.

Fy (LBS)

-39

'11

'5

'6',

(LBS)

(FT-LBS)

Ny (FT-LBS)

Xg (FT LBS)

UPSET (+)

UPSET

-)

EMERGENCY(+)

EMERGENCY(-)

THERMAL I (MORWAL)

THERMAL II IACCIDEYf)

THERMAL III lMST.ACCIDEYn X

(in) 0.00 DISPLACEMENTS Y

(in) 0.00 5

(in)

-0.0398 NOTES: l. +X ~ NORTH'Y ~ UP,

+5

~ EAST.

2 ~

3 ~

CAROLINA POWER fi LIGHT COXPANY HARRIS NUCLEAR PLANT PCH/PID IIUMBBR PCR-6547 PAOB 141-1A IIBVISIOH SVBJBCI SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS'IUONATOR'S MIIALS/DATB

~-"~-~z CHBCKBII'SMIIALS/DATB C(g, C,~

HANGER NO.CS- -

59 NODE PT.

ISO NO.

-59 SUPPORT SYSTEM CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD

& TAD DBE SAM OBE(Inertia)

DBE(Inertia)

UPSET (+)

UPSET

-)

EMERGENCY(+)

EMERGENCY(-)

r~

(LBS )

-98.

15.

24' (LBS)

-63.

54.

25.

44 rz (LBS)

(FT-LBS )

lly (FT-LBS)

(FT-LBS)

THERMAL I (NOkMAL)

THERMAL ZZ IACCIDEHTl THERMAL IZI oosT Acc/DEYn X

(in) 0.00 DZSPLACENENTS Y

(in) 0.00 S

(in)

-0.0116 NOTES: 1.

+X ~ NORTH,

+Y ~ UP,

+Z ~ EAST.

3.

CAROLINA POWER

~ LIGHT COMPANY PLANT HARRIS NUCLEAR PLANT CALCULATIONNUMBER 141-1A PCN/PID NUMBER PCR-6547 PAOE REVISION SUBJECI'I CHARGING PUMP ALTERNATE MINE-FLOW LINE, RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

ORIOINATOR'S INITIALS/DATE P3 a~

CHECKER'S INITIALS/l)ATE HANGER NO.CS- -4 5

ISO NO 6-CS-9 SUPPORT SYSTEN CONDITION DEADWEIGHT THERMAL I THERMAL IZ THERMAL III PAD Ec TAD DBE SAM OBE(Ine).tia)

DBE(Inertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

THERMAL I 0/OkMAL)

THERMAL II (ACC)DEYn THERMAL III

/)0$f.ACCIDD)n Px (LBS) 185.

49.

72.

X (in) 0.00 Fy (LBS)

-30.

-10.

19

'1.

DZSPLACEMENTS Y

(in) 0.00 r~

(LBS) 5 (in)

-0.0457 N)

(PT-LBS)

(FT-LBS)

(tT-LBS)

NOTES!

1

+X ~ NORTH)

+Y ~ UP)

+Z > EAST.

3 2 ~

3 ~

CAROLINA PONE+

fg LIGHT COlCP7LNY PLANT HARRIS NUCLEAR PLANT PCN/PID NllMBBR PCR-6547 PAOB 141-1A RBVLSION SUBJBCI'I CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

ORIOINATOR'S INITIALS/DATB 0 ~

CHPXKFJI'S INITIALS/DATB Q a(~s)%'~

HANGER NO.CS-H-4253 ISO NO.

A-236-CS-59 SUPPORT SYSTEX CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD

& TAD DBE SAM OBE(Inertia)

DBE(Inertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

r, (LBS)

-180.

36.

53.

X (in)

Fy (LBS) 72 ~

43

'9

'0.

401 DISPLACENENTS Y

(in) rz (LBS) le (FT-LBS) le

( FT-LBS) le (FT-LBS)

THERMAL I OIOM4ALl THERMAL IZ

{ACCUSANT)

THERMAL-ZIZ 0.00 0.00

-0.0133 NOTES: 1.

+X ~ NORTH/

+Y ~ UP(

+Z < EAST.

2 ~

3 ~

CAROLINA XOWZR a LIGHT COXXmx PLANT HARRIS NUCLEAR PLANT PCN/PID NUMBER PCR-6547 SUBJECT SI CHARGING PUMP ALTERNATE MINI-FLOW LINE) RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

CALCULATIONNl/MBER 141-'

PAOE 0RIOINATOR'S INITIALS/DATE 8-"3-'l~

CHECKER'S INITIALS/DATE

~]~ IIC~

HANGER NO.CS- -4 4

ZSO NO. CS-59 SUPPORT SYSTEM CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD

& TAD DBE SAM OBE(Inertia)

DBE(Inertia)

UPSET (+)

UPSET

-)

EMERGENCY(+)

EMERGENCY(-)

THERMAL I (NOkMALl THERMAL ZZ (ACCIDEÃn THERMAL ZZZ

@Off-ACCJDE)n Fx (LBS) 0.1084 (LBS)

-171.

74.

122.

DZSPLACEXENTS Y

(in) 0.00 F~

(LBS) 5 (in)

-0.0860 le (FT-LBS) le (FT-LBS)

Nz (FT-LBS)

NOTES'.

+X ~ NORTH)

+Y ~ UP)

+5 < EAST.

3.

ClQtOLZMA POWER fa LIGHT COXPAÃY PLANT HARRIS NUCLEAR PLANT PCg/PID NUMBER PCR-6547 FAOE 141-1A REVISION SUBJECT SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED)

FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

ORJONATOR'S INITIALS/DATE c.g q-zs-~z CHECKER'S INITIALS/DAYE p~

HANGER NO.CS- -4 45 NODE PT.84 ISO NO. CS-59 SUPPORT SYSTEX CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD SI TAD DBE SAM OBE(Inertia)

DBE(Inertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

THERMAL I (NOLWALI THERMAL II IACCDEÃn THERMAL III (POST ACCIDEÃTI Fx (LBS)

(in) 0.0443 Fy (LBS)

-89

'5.

58.

DISPLACENQPZS Y

(in) 0.00 (LBS)

-53.

34.

50.

53

~

Boa 10$

S (in) 0.00 Nx (FT LBS)

(FT-LBS) le

( FT-LBS )

NOTES:

1.

+X > NORTH(

+Y ~ UP)

+Z ~ EAST.

2 ~

3 ~

CAROL INA llOÃER fi LIGHT COHP ANY PLANT HARRIS NUCLEAR PLANT pCN/FG) NL.ABER PCR-654'7 PAOE 141-1A SVBJECr SI CHARGING PUKP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED/

FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

ORlONATOR'S lNIALS/DATE c-0 R-~-qz.

CHECKER'5 MTIALS/DATE

~)wsP~

HANGER NO.CS--

ISO NO.

6-

-5 SUPPORT SYSTEM CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD

& TAD DBE SAM OBE(Inertia)

DBE(Inertia) rx (LBS) r (LBS) 3 7 ~

2 ~

32

'3'z (LBS) le (FT-LBS)

Ny (FT-LBS)

Xz (FT-LBS)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

THERMAL I OlOlQlALl THERMAL II x

(in)

-0.0127 DISPLACEMENTS Y

(in) 0.00 (in)

-0.0641 THERMAL III posT.AcclDExn NOTES 1

+X + NORTH'Y +

UPg

+Z + EAST 2 ~

3 ~

CAROLINA POWER fa LIGHT COMPANY HARRIS NUCLEAR PLANT PCN/FID NUMBER PCR-6547 I'A0E 141-1A REVISION SUBJECT SI CHARGING PUMP ALTERNATE MINI-FLOW LINE/ RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

ORIOINATOR'S INITIALS/DATE C

9- ~~z.

CIKCKER'S MTIALS/DATE l> 3s HANGER NO.CS-H-4237 NODE PT.8460 ISO NO.

1A-236-CS-59 SUPPORT SYSTBX CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD

& TAD DBE SAM OBE(Inertia)

DBE(Inertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

THERMAL I (NOkMAU THERMAL II

{ACCIDENT)

THERMAL ZZZ POSI'ACCIDENT)

Fg (LBS) 32 ~

39.

56.

0.00 r

(LBS )

-66.

-4.

36.

56.

fz(

)

2'I SPLACEMENTS Y

(in) 0.00 Fg (LBS) 5 (in)

-0.0454 (FT-LBS) lCy (FT-LBS)

( FT-LBS )

NOTES l

+X ~

NORTH@

+Y ~ UP g

+Z ~ EAST 2 ~

3.

CAROLINA POB(ER Si LIGHT COMPANY PLANT HARRIS NUCLEAR PLANT CALCULATIONHUMBER 141-1A pCN/pID NUMBER PCR-6547 PAOE REVISION SUBJECT SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS'RIOINATOR'S INITIALS/DATE 4 s-zs-e~

CHECKER'S INITIALS/DATE

~l~1'ANGER NO.CS-H-4 39 NODE PT.7730 ISO NO. CS-59 SUPPORT SYSTEN CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD 6 TAD DBE SAM OBE(Inertia)

DBE(Inertia) rx (LBS )

(LBS)

-134.

-14.

93.

143.

r~

(LBS)

(FT-LBS)

Ny (FT-LBS)

(FT-LBS)

UPSET (+)

UPSET

-)

EMERGENCY(+)

EMERGENCY(-)

THERMAL I INOkMALI THERMAL II THERMAL III (10'CClDENT) 0.0086 24'ISPLACEMENTS Y

(in) 0.00 5

(in) 0.0296 NOTES 1

+X a NORTH(

+Y a UP)

+5

~ EAST 3.

CAROLINA POSER fc LIGHT COMPANY HARRIS NUCLEAR PLANT PCN/PID NUMBER PCR-6547 PAOE 141-1A REVISION SUBJECT SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

ORIGINATOR'S INITIALS/DATE CHECKER'S D/ITIALS/DATE g. ~ij~lR~

HANGER NO.

ISO NO.

-C SUPPORT SYSTEX CONDITION DEADWEIGHT THERMAL I THERMAL II THERMAL III PAD

& TAD DBE SAM OBE(Inertia)

DBE (Inertia)

UPSET (+)

UPSET (-

EMERGENCY +)

EMERGENCY(-)

" Fz (LBS)

Fy (LBS )

-10.

-6.

4 ~

7 ~

20.

20.

23.

23',

(LBS)

-1.

7 ~

2 ~

4.

8.

8.

10.

10.

llz (FT-LBS) lip (FT-LBS)

(FT LBS)

THERMAL I P(OkWAll THERMAL II (A~

THERMAL III POST ACCRDfTI

~ I (in) 0.00 D IS PLACEKENTS Y

(in) 0.00 5

(in) 0.00 NOTES: 1.

+X > NORTH,

+Y ~ UP(

+Z ~ EAST.

2 ~

3 ~

ChROLINh POKER

& LIGHT CONPhNY P1AHT HARRIS NUCLEAR PLANT PCN/PID NUMEER PCR-6547 PAOE 14 1-lA REVISION SUBJECT SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED

'ITH LEAD BLANKETS.

ORIOINATOR'9INITIALS/DATE Ol-ZS-eZ, CHECKER'S INITIALS/DATE ISO NO.

A-36-CS-58 SUPPORT SYSTEX CONDZTION DEADWEIGHT THERMAL I THERMAL II THERMAL IZZ PAD

& TAD DBE SAM OBE(Inertia)

DBE(Inertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

THERMAL Z QIORMAII THERMAL IZ

~

(LBS)

X (in) 0.00 Fy (LBS)

-13

'6.

12.

20.

31.

31.

39.

39.

DZSPLACENE)lTS Y

(in) 0.00 F~

(LBS)

-1 ~

36.

53.

37

'7

'4.

54.

5 (in) 0.00 Ng (FT LBS)

(FT-LBS)

( FT-LBS )

THERMAL ZZI EST.ACCDEYn NOTES: 1.

+X a NORTH(

+Y a UP)

+Z ~ EAST.

2 ~

3 ~

CAROLINA POWER 4 LIGHT COHPAHY HARRIS NUCLEAR PLANT PCN/PID NUMBER PCR-6547 PAOE 141-1A REYISIOtt SUBJECT SI CHARGING PUMP ALTERNATE MINI-FLOW LINE RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

La~a,w<D

'Loam F(Lo~ ('I's. iui-L(s

) Hi.-2 A~o ).4L. Z..

ORIGINATOR'S MTIALSJDATE C-.',

~.-'3~=.

CHECKER'S MTIALS/DATE 9~ a) )3(~

HANGER NO.CS- -4403 NODE PT.

ZSO NO.

6-S-59 SUPPORT SYSTEN CONDITION F,

(LBS )

F (LBS)

FR (LBS)

Ng (FT-LBS) l4y (FT-LBS)

(FT-LBS)

DEADWEIGHT ILn

-406.

2 ~

5l

-7 l.

26.

THERMAL I LuLo 104.

-35.

-L l I 5 j

-2.>

THERMAL II (Eb ~O K<(.t:-itu(.~ cl o~

THERMAL III PAD 6 TAD DBE SAM OBE(Inertia)

DBE(Inertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

( I.iS)-HS 86.

41 138.

05

~bb:~s)= Bo ll 2.7.

162.

55 2

~

l5'l 'l5 50 Lo 159.

101.

92.

45.

H Zws S-l

'l4 258.

161.

Ol 1o l

141.

72.

~h..uS3=2.bh II'l(I~3.- 5 RS (i.to5~=

THERMAL I (NakMALl THERMAL ZI Z

(in) 0.00 DZSPLACENENTS Y

(in) 0.00 5

(in) 0.00 Me,<uC.C, (S,~~< Zoaco.

L4a~: EH'8, 2u l-Zh-lZ& el1loo.

( a4',QL. l Ou LKBl-S 0 l'~Zev LR<l l4 T. ha 9 5 BS 2 lZ:s I e.v.

THERMAL IIZ (t0$T.ACCQKMn NOTES:. 1.

+X > NORTH(

+Y > UPt

+Z > EAST.

2-SEE, Amus ('a.

5+i.->

FOc E,eo o,=ua~~u, 3.

CAROLINA POSER R LIGHT COMPANY I'LANT HARRIS NUCLEAR PLANT 141-1A PCR-6547 PACE REVISION SUBJBCf SI CHARGING PUMP ALTERNATE MINI-FLOW LINE RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

Loea=u.c n Loans Fe.oe.

C ops. lHl-LO L.Hl-l 4e ORIOINATOR'S INITIALS/DATE cA 9-z~~~

CHECKER'S D/ITIALS/DATE Ilig.~'~,

HANGER NO.CS-H-4406 ISO NO.

3 -CS-59 SUPPORT SYSTEX CONDITION DEADWEIGHT Fx (LBS)

Fy (LBS)

Sl 5

-406.

Fg (LBS)

Xg (FT-LBS)

SL ZO (FT-LBS)

Ng (FT-LBS)

-24.

ml THERMAL I

'LOI THERMAL II 7 ~

so%

Zh -5 5H

-45.

83.

-5%

Zlo sm 17.

-25.

-48.

9 MCt %lg\\I

~

%THERMAL III PAD 6 TAD DBE SAM OBE(Inertia)

~7,

. 'lip)%

84.

161.

Z.S I 100.

to'E 54.

SL 27.

43

'BE(Inertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

136.

5h Ih 300 285.

173.

IO 93.

47.

70.

THERMAL I 0/0kNAQ THERMAL II (ACCQKIVQ THERMAL III POST.ACC!DENT) 0.00 DISPLACE)69iTS 0.00 5

(in) 0.00 Lo as~~c Q~~c

( oac~

CAu: l%L.N Ou W.ZSR~ > 0"L I'Os t au'H'L-L. Ow L".EI.bi ~~ 4I5S v m Col.c.: LSL Z Ow 6-Ih-5K 2. 'O'.Yl V.W NOTES: 1.

+X ~ NORTH,

+Y ~ UP,

+Z ~ EAST.

3.

CAROLINA PONER a LIGHT COMPANY HARRIS NUCLEAR PLANT

~/PID NUMBER PCR-6547 I'AOE 141-1A REl/ISIOH SUBJECT SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS~

C oeazoc.O Loaoh 6tc~ ('at 1 Rl-i.A l lk,-l O~s 161-Z.

ORIONATOR'S MTIALS/DATE

( 4 e-~~-~

CHECKER'S MYI/CS/DATE C1) l ) )S~

HANGER NO.

NODE PT.

ISO NO.

SUPPORT SYSTEX CONDITION DEADWEIGHT THERMAL I THERMAL II (%.l (LBS) 0 2 ~

93.

Fy (LBS)

-q5

~l

-364. -ll

-42.

i~'L-4 f.hL..Z.

F, (LBS) z.

53.

-S 445.

Ng (FT-LBS)

G 43.

~l L'I 284.

Ny (FT LBS) 2.

0 46.

5 318.

Ng (FT-LBS)

IC) -21.

P1 -36.

l4crc 1 Kl.t'uhi %L.~

~ HERMAL III PAD C) TAD DBE SAM OBE(Inertia)

DBE ( Inertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

lq,5'b.l.SN=

Z, l 84.

VS 2.'1 135.

OO 5~(i.l))N=QQ 1

167.

le L1 290.

B~z SCCA.ml~ hM

'\\+5 284.

2n5 413.

2Mb. cA:'L&I

~ \\

212.

303.

( 5CI 214.

lQ 302.

I OL"I 3QI I

~DPI

-~lAl),l 74.

110.

THERMAL I 0/0kMAl)

THERMAL ZZ IACClDEYn THERMAL ZZZ nfl'ACCIDEYn 0.00 DZSPLACEMENTS Y

(in) 0.00 5

(ia) 0.00 C.OMfhS.llC.O A~~C-LORQbl C.a~'si-ia ou al.aolz. > W':o<

Cau:. i.Sa.L. QO 2-3X-E/Il ~> 6lSS 7 e.

"Oui )41-'L Oe 4-LS-65K IZ: w l Kt.

NOTES: 1.

+X > NORTH)

+Y > UP)

+5 < EAST.

3.

C dC p

~l

g. 5W Mr r P

~ W~mn c.

f= 5/WJ

/I S/=

=

CMw 8 8W C'o Ad -+J-ods z

ohio y 9b

Page'~

of~

NED INTERDISCIPLINE REVIEW REQUEST (IRR)

To:

From:.

IRRg:

MOD/RET/PCR/PCNO Unit/Subunit Unit/Subunit Plant'~

Details of Review Request:

PLEASE PROVIDE PERMANENT SHIELDING FOR THE 3 STRAINERS DESIGNED FOR THIS MODIFICATION. A FREE STANDING ANCHORED HOUSING IS PREFERABLE.

Response

Required By:

Authorized Manhours esponse/Justification:

Phase:

Activity:

/<re <~c>A 5g g/d, >y A&y.~g gree++

~w g1~H.

+Row'51 re ~

~s g- >~

~~ 4>

Ps>p~

yV~ /~f7-g-rod@

Au / ~ 5 =Md Attachments (list): 5P.-

AERY?

C-/uc C S4r~~ ~ 4 S+~Cg Responsible

/r,~

Supervisor/Date Actual Man-hours a.xpended I

Distribution:

NED GuidelineNo.

E-24 Revision 3 (6/90)