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)

Text

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Calc. No. SZ-0044 Page No. 1 of 13 Revision 0 System File No. 2080 LIST OF EFFECTIVE PAGES Page Rev.

1 0 2 0 3 0 4 0 5 0 6 0 7 0 8 0 9 0 10 0 11 0 12 0 13 0 TABLE OF CONTENTS Page List of Effective Pages Table of Contents PURPOSE LIST OF REFERENCES III'ODY OF CALCULATION 1.0 Assumptions and Bases 2.0 Strainer Basket Design Calculation 3.0 Strainer/Strainer Piping Friction Head Loss 4.0 Impact of New Strainer/Strainer Piping on Recirc Line Friction Head Loss and Flow Rate IV. CONCLUSIONS 13 V. ATTACHMEKZS 13 A. Design Verification Record(s) and Design Review Check Sheet(s), as appropriate

Calc. No. SX-0044 Page No. 2 of 13 Revision 0 System File No. 2080 I. PURPOSE 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.

Calc. No. SI-0044 Page No. 3 of 13 Revision 0 System File No. 2080 Assumptions and Bases (cont'd)

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 capture will assumed that the total amount of debris which each strainer 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 6P used in this analysis

((2710). 2.3088 63) ft = 6193.8 adjusted 6P (6256.8 - 6193.8) 1.007 4 6256.8 ft 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.

Calc. No. SX-0044 Page No. 4 of 13 Revision 0 System File No. 2080 2.0 Strainer Basket Design Calculation 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) 2 A 3. vr A = 150.796. in debris 4 debris 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 pipe

= 1.687 in A:=

pipe 2.241 in 2

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 2 basket [ debris pipe J A = 160. 689. in basket 2

BasketArea:= 161.0. 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 BasketCircumf = 14.13'i in BasketArea BasketLength : BasketLength = 11.388 in BasketCircumf 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 HousingXD BasketOD Clearance 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 rows Columns:= (12 in) ~

4 Rows  := (14 in) 4 in in Columns = 48 columns Rows = 56 rows TotalHoles := Columns Rows HcleeperSH?ncn  := 16 holes 2

TotalHoles = 2688 holes 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:

2 Hol~ 2 A A = 0.012272 in hole hole HoleArea := A TotalHoles hole HoleArea = 32.987 i' 2 MetalArea := BasketArea HoleArea 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 2 covered debris A = 150.796 in covered A  := BasketArea - A 2 uncovered covered A = 18.85 in uncovered 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:

Q design gpm HoleQ HoleQ 0. 022321 unclogged TotalHoles unclogged hole Q

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

HoleQ unclogged V = 0.5836.

unclogged A unclogged sec hole hole HoleQ clogged

,V V '= 5.6988.

clogged A clogged sec hole 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,  := Hl + Hl n piping pipe fittings 3.2 From Assumption 1.1 and Ref. 2, the water density and kinematic viscosity at 90 degrees F are identified:

lb 2 p  := 62.11 -5 3 v 0.826 10 ft kin 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 R 0.00142264 pipe ID pipe pipe 3.5 The flow velocity and Reynolds number for the piping is determined from the Q in Step 3.3:

Vel Q

test Vel = 9.163 ft pipe A pipe sec pipe Vel ID pipe pipe Nre Nre = 155945 pipe v pipe kin 3.6 From Assumption 1.3 and Ref. 1, the friction factor is determined:

j  := 0 ..3 0

.015 f 0.015 j+1 R 0.02313 2'og pipe 2.51 0.02282 F ~

f3

+ 0.02283 piping 3' .5 Nre f F = 0.023 pipe -

j 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  := -21.5 in length

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  := F K. = -0.291 pipe piping ID pipe pipe K ~

0 fittings K = K + K K ,0.291 piping pipe fittings piping 3.9 From Ref. 2, the friction head loss of the piping is found:

Vel pipe Hl =K Hl' -0.38 piping piping 2 ~

g piping 3.10 From Refs. 5 and 3, the inside diameter of the basket is found:

BasketID := 4.26 in 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 B B = 0.396 increaser BasketID increaser K 1-B K 0.711 entrance increaser entrance Vel pipe Hl  := K Hl = 0.928 entrance entrance 2' 'ntrance

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 2 BasketArea BasketArea = 0. 063112 in hole TotalHoles hole Plate4 = 0.283 in 4 BasketArea hole Plat@ Hol~ = 0.125 in The friction head loss is calculated for two bounding flow conditions: a fully clogged strainer basket. and a clean basket with no debris.

Q test gpm HoleQ HoleQ 0.02381.

unclogged TotalHoles unclogged hole Q

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

HoleQ unclogged V V 0. 6225.

unclogged A unclogged sec hole hole HoleQ clogged V V 6.0787 clogged A clogged sec hole hole

Calc. No. SI-0044 Page No. 10 of 13 Revision 0 System File No. 2080 3.15 The Reynolds numbers are determined from the velocities in Step 3.13:

V .

Hol~

unclogged Nre Nre = 785 unclogged v unclogged kin V . Hol~

clogged Nre Nre = 7666 clogged v clogged kin 3.16 From Ref. 2, the basket K values and friction head losses are determined:

Hol~ ,C .67 8 8 = 0.441 unclogged orifice Plateful orifice C .62

- clogged 1

8'rifice K K = 47.463 unclogged unclogged C 8 unclogged orifice 1-8 ~

orifice K K = 55.427 clogged clogged C 8 clogged orifice V

unclogged Hl  := K Hl = 0.286 unclogged unclogged 2'g unclogged V

clogged Hl  := K 2'

Hl = 31.828 "ft clogged clogged 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 Vel pipe Hl =K Hl = 0.652 exit exit 2' exit 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 entrance

+ Hl + Hl exit i 1.15 unclogged L piping unclogged J Hl unclogged

= 1.709 ft dP  := Hl dP = 0.737 psig unclogged unclogged unclogged 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 Hl + Hl + Hl + Hl exit ]J 1.15 clogged piping entrance clogged Hl clogged

= 37.982. ft

= 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 will still 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 dP 2710 psig total

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 dP dP 2709.263 psig recirc total unclogged recirc dP recirc NewQ ~

Q NewQ = 63.991 gpm unclogged test dP unclogged total Q NewQ test unclogged 0.014 Q

test 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 dP = 2693.617 psig recirc total clogged recirc dP recirc NewQ o Q NewQ = 63.806 gpm clogged test dP clogged total Q NewQ test clogged 0.303 4 Q

test

, 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 Page 1 ltmtrLs:ti~ to Verification Persornel Plant [~Q, (Class A)

Pro ject [ ) Seismic (Class g)

F i le Ho. Level [ ) FP-Q (Class 0)

Document Ho. S Rev CI [ ) 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 Disci line Hechani ca l C i v i l Structural [)

HVAC [] Seismic Equip. Qual. [)

Electrical [) Civil Stress [)

>ac [.) Fire Protection [)

Envirom>>ntal Qualification [)

Huaan Factors [)

Haterials [)

[)

Other [)

Ver)fioat'ion Hethods Used:

M Design Revie~ [ ] Alternate Calculations "

[') Qualification Testing Design Docuaent Acceptahlr: Tr' Ho [ ) - cannents attached.

Design Verifier Da'te ~j Acksxwledgement of Vr~H'icationt (OPE) Date c ~ pp /i/2 l]I. Resolutim of 'C~st Comnents Resolved (See Attached):

(RE) Date Action taken s>>kes Design Documents Acceptable:

Design Verifier Oa'te (DPE) Date HED procedure 3.3/Rev. 5D

Page 1 DES EGN REVIEW CHECK SHEET Plant Document Type ~Lc.

Project Document No.

File 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 sv-n f9 Document No.

Revision

11. Have adequate maintenance features and requirements been specified?

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 test requirements been specified?

~ ~

16. Are adequate storing, handling, cleaning, shipping, and identification requirements specified? ~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 Date (Design Verifier)

II. Phi- +p>'~big g K ~ Cgc<>id (g. ilaw Qfl JW lo ~~ > C

SYSTEM/ 2005 CALC. TYPE 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 No SAFETY RELATED: 5 0 SEISMIC APPROVAL REV. PREPARED BY VERIFIED BY PROJ. ENGINEER PRIN. ENGINEER NO. DATE DATE DATE 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 REV PAGE REV PAGE REV 1 0 2 0 3 0 4 0 5 0 6 0 7 0 8 0 9 0 10 0 11 0 12 0 13 0 14 0 15 0 16 0 17 0 18 0 ATTACHMENTS

Table'of Contents Page No. ii Calculation No. HNP-I/INST-1044 Rev. 0 Pacae No.

1.0 OBJECTIVE o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 1 2.0 LOOP FUNCTIONAL DESCRIPTION................ 1

3.0 REFERENCES

....................:.......... 1 4.0 INPUTS AND ASSUMPTIONS .................... 5 5.0 DETERMINATIONOF UNCERTAINTIES............. 7 7 o0 FIGURES o ~ ~ ~ ~ ~ o o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 15

Pnmputed b~. Date: Calculation ID:

CAROLINA POWER Si LIGHT COMPJLNY HNP-I/INST-1044 Date: Pg. 1 Rev. 0 Chocke~'AR/PZD No.: CALCULATION SHEET 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 CWD" ~

R5 "CVCS MiniFlow Valve 2CS-V757SB-1 3 ~ 1.5 CAR-2166-B-431 Sh.L-74 R6 "RVLZS Instrument Installation Detail" 3 '.6 CAR-2166-B-431 Sh.L-75 Detail" R5 "RVLZS Instrument Installation 3.1 ~ 7 CAR-2166-B-431 Sh.L-78 R2 "RVLIS Instrument Installation Detail" 3~1~8 CAR-2166-B-432 RSO "Instrument Index" 3 '.9 CAR-2166-G-436 Sh. 2 R10 Arrangement".

"Reactor Aux. Building El. 236

'nstrument 3ol ~ 10 CAR-2166-G-437 Sh.3 Rll "Reactor Aux. Building Arrangement". E1.236'nstrument 3 '.11 CAR-2166-S-PRC0402 Rl "RCS Wide Range Pressure Loop 3 Loop Diagram".

3. 1. 12 CAR-2166-S-PRC0402/1 RO "RCS Wide Range Press'ure Loop 3 Loop Diagram".

Date: Calculation ZD:

CAROLINA POWER 4 LIGHT COMPANY HNP-I/INST-1044

~her I or4 Date: Rev. 0 Pg. 2 TAR/PID No.: CALCULATION SHEET 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 CAR-2166-S-PRC0403 Rl "RCS Wide Range Pressure Loop 1 Loop Diagram".

3 ~ 1 ~ 14 CAR-2166-S-2500 R7 EQDP "Section 8.0 Sensors".

3 ' '5 CAR-2166-S-9000 R3 "Post Accident Monitoring Equipment, Regulation Guide 1.97".

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

3 '.17 Emdracs 1364-46574 Sh.22 R8 "RCS Wide Range Pressure ZWD".

P-402 3 ' '8 Emdracs 1364-46577 Sh.8 R6 "RCS Wide Range Pressure ZWD" ~

P-403 3 ' ~ 19 Emdracs 1364-92079 Sh.ll R5 "RCS Wide Range Pressure P-402 ZWD".

3.1.20 Emdracs 1364-47254 R4 "RVLZS Transmitters Group A".

3 ' '1 Emdracs 1364-52638 R2 "RVLZS Transmitters Group B".

3 ~ 1 ~ 22 Emdracs 1364-52497 R3 "RCS Flow Diagram".

3.1 ~ 23 Emdracs 1364-B-0070 R45 "Line As-Built Master List".

3 '.24 CAR-2166-B-431 Sh.LP-01 R6 "Typical Pressurizer Instrument Installation Detail" 3 ~ 1 ~ 25 Emdracs 1364-92079 Sh.9 R4 "Pressurizer Pressure P-455 ZWD" ~

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

3 '.27 Emdracs 1364-46575 Sh.19 R7 ZWD".

"Pressurizer Pressure P-456 3 ~ 1 ~ 28 Emdracs 1364-46576 Sh.15 R7 "Pressurizer Pressure P-457 IWD".

3.2 SHNPP Updated FSAR 3.2. 1 Section 1.8 "Conformance to USNRC Reg Guide 1.105".

3 F 2 Section 9.4.0 R27 "Air Conditioning, Heating, Cooling, and, Ventilation System".

3 ~2 ~3 Figure 3.11B-4 R40 "Reactor Aux. Building Parameters During Normal 6 Post Accident E1.236'nvironmental Environments".

gmruot csR Date: Calculation ZD:

CAROLINA POWER & LIGHT COMPANY HNP-I/INST-1044 Date: Pg. 3 Rev. 0 TAR/PZD No.: CALCULATION SHEET 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 Parameters During Normal & Post Accident E1.305'nvironmental Environments".

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

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

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

3 ~3 ~2 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 VM-ONY "ZTT Barton Technical Manual" or VM-BFL "Tobar Technical Manual" and including latest vendor literature.

3.5 ~ 2 VM-OSE "Westinghouse RVLIS Manual".

3 ~ 5.3 VM-PYC/PNO "Westinghouse Analog Controls".

3 ~5 ~4 Westinghouse WCAP-8687 Supp.2-E13 Rev.2 "Equipment Qualification Test Report Process Protection System".

3+5 ~ 5 "Westinghouse Setpoint Methodology for Protection Systems Shearon Harris, Rev. 1" 3~5.6 VM-ZSP-V02 "Charging Safety Injection Pumps".

3.5.7 Westinghouse CQL-TAC-01 S.O. 280 "High Head Safety Injection System".

3.5.8 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 i t- ad Date: Calculation ID:

CAROLINA POWER 5 LIGHT COMPANY HNP-I/INST-1044

@ger 1 > 4a. ~

Date: Pg. 4 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. 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 MST-Z0081 R2 "RCS Wide Range Pressure P-403 Calibration".

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

3.6.4 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 USNRC Reg. Guide 1.105 "Instrument Setpoints For Safety Related Systems".

3.7.4 ASME R5 "Steam Tables".

3.8 Other References 3~8~1 Equipment Data Base System (EDBS) 3~8~2 PCR-5322 "Replacement of Reactor Vessel Level Instrumentation".

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

3 '.4 Calculation HNP-I/INST-1003 RO "Pressurizer Pressure Error Analysis".

Date: Calculation ID:

CAROLZNA POWER & LIGHT COMPANY HNP-I/INST-1044 Date: Pg. 5 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 ~ 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 ' 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.

4.7 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 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).

4.9 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 '- Date: Calculation ID:

HNP-I/INST-1044 CAROLINA POWER fc LIGHT COMPANY Ch p>>~ad ~- ~

Date: Rev. 0 Pg. 6 TAhga ID No.: CALCULATION SHEET 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 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 4 ~ 12 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].

I ~,4 qy>> Date: Calculation ID:

CAROLINA POWER Sc LIGHT COMPANY HNP-I/INST-1044 Date: Pg. 7 Rev. 0 TAR/PID No.: ,'ALCULATION SHEET 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 Head Correction - The errors due to head correction are insignificant compared to the high pressures being measured

[Ref. 3.6, Assumption 4.3).

5~1~2 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"""~ ~" Date: Calculation ID:

CAROLINA POWER fc LIGHT COMPANY HNP-I/INST-1044 I PCL 4 +ye Date: Pg. 8 Rev. 0 I

TAR/PID No.: CALCULATION SHEET File:

Project

Title:

Shearon Harris Setpoints Calculation

Title:

RCS Wide Range Pressure: Accuracy and Setpoint Calculation Status: Prelim. Q Final g Void Q

'c 5 'A.7 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 calibration of this instrument depends on two MQTE The 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 2A. 10 Calibration Tolerance - Per Ref. 3.6, the allowable range at 5 ~

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

Date: Calculation ID:

CAROLINA POWER 4 LIGHT COMPANY HNP-I/INST-1044

~ i ~'4pr4 4 Date: 9,

~

Pg. 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. 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].

Date: Calculation ID:

CAROLINA POWER fc LIGHT COMPANY HNP-I/INST-1044 Chr ~.~R bv ~

Date: Pg. 10 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. P Final ~ Void P 5.2B.9 Measurement and Test E i ment Inaccuracies calibration of this instrument depends on two MGTE The 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 calibration of this instrument i ment Uncertainties The 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 Date: Calculation ID:

CAROLINA POWER Sc LIGHT COMPANY HNP-I/INST-1044 r i<or\ Date: Pg. 11 Rev. 0 TAR/PID oo.: CALCULATION SHEET 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.

span, which accounts 3.5.5, the rack for the combined drift is 11.00% of 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" Date: Calculation ID:

HNP-I/INST-1044 CAROLINA POWER fc LIGHT COMPANY I ~'4onQp4 I; ~ ~ ~ Date: Pg. 12 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. 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 s0.50 ICTUS Dr.i ft s2.00

%0.60 Temper'atur'e'eismic s0.50 Poi7er,". Relil'atTon s0.03 in:,'. t0.50 H&TEout s0.50 Ci'l'db'riti'ori':Tb l'eranciei +0.50 -0.50 SighaU:::1'sol'i'to'r'."::::::: Mestin'gho'use'::Model::::kt'PZ':::::Ql'P3::::::::::::::::::::::::::::::::::::.

R'e'fiir'en'ca:: a0.10

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

Suit'ch ':::: Me'sf iiighou'se:'ih'xhil::::)NL1'".:::::::::::::::::::::::::::

Refi;r'e'n'c'ii': A'c'ciir'iicy.'."". s0.35 N&TEih s0.50 Cal'ibrat'ion +0.50 -0.50 Rack: Drift s1.00 Rack'TeeIperature s0.50 Grand .Tote ls'f,': (Randai),,: x6.9934 Cr'and:::Total's:::bf,"Rii'ndaiii::.an'd;:Bia's': s2.64 +1.00 -1.00

Chan'nel.:::Total'R's'ndo'in)+(Bias>' '::::::::::::: s3.64

Dat,e: Calculation ID:

CAROLINA POWER tc LIGHT COMPANY HNP-I/INST-1044

@ban 4~8 4 ~

Date: 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 Date: Calculation ZD:

CAROLINA POWER fe LIGHT COMPANY HNP-I/INST-1044 Chppv Date: Pg. 14 Rev. 0 1

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

SP ~ 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 Date: Calculation ID:

CAROLINA POWER 4 LIGHT COMPANY HNP-I/INST-1044 1

Checkedi Date: Pg. 15 Rev. 0 I

I TAR/P ID No ~ CALCULATION SHEET 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 ~

Date: Calculation ZD:

I HNP-Z/ZNST-1044 CAROLZNA POWER a LIGHT COMPANY I~ r I

CIl liar's Lot+ Date: Pg. 16 Rev. 0 TAR/PZD No.: CALCULATZON SHEET 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: Calculation ID:

CAROLINA POWER 5 LIGHT COMPANY HNP-I/INST-1044 Date: Pg. 17 Rev. 0 CALCULATION SHEET File:

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 Date: Calculation ID:

CAROLINA POWER Sc LIGHT COMPANY HNP-I/INST-1044 PQ~plr~ ~ 4 ~

Date: Pg. 18 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. 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 protection of the weakest charging/safety injection pump (CSZP) ensure 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 Page 1 I. ]nstrcs:time to Verification Persocnel Plant SHw t'P W 0 (Class A)

Project E~ o/ LCS a [ ] Seismic (CLass 8)

File Ko. g Io- Z F7- )O level [ ) FP.D (Class O)

D~~t Ko.POP-2 r- 0 Rev C7 [ ] 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 Appl i csbi l i ty Disci line Disci line Hechsnical Civil Structural []

KVAC Seismic Equip. Dual. []

Electrical Civil Stress []

]AC Fire Protection []

Envirormentsl Qualification []

Kcmcsn Factors []

Haterials []

[)

Other []

Verification Hethods Used:

W Design Revie<< [ ] Alternate Calculations [ ] qualification Testing Design Verifier ~

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

Date zj ll]. Resolution of C~tst Ccmcsenty P>>-c v. '"~ -bed) t (RE) Date ActioJYtsken makes of icu( nWi Design Verifier Date zl 2 (OPE) z Jpz KED Procedure 3.3/Rev. 50

Page 2 DISCIPLIKE DESIGK VERI FICATILA RECITED CONHEHT SHEET Plant K&iUPP Project M AC File Ho. p-z- ~~r'-)~Vg Docuwnt go. PIAIPZ+I TIO'Y Rev 0 This sheet is only required shen contents are being made.

Ccaaent Resolved Ho. Comnent Resolution Initial/Date

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d+AiU&E 7hAu6Cou7

~S ochre7 o C Z8 z/ly'z HED Procedure 3.3/Rev. 50

Page 1 DESIGN REVIEW CHECK SHEET Plant ~h N P'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? gES (

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

5. Has applicable construction and operating experience been considered?

~

~

6. Have design interface requirements been satisfied? $65(

7. Was an appropriate design method used? yE.&(

8. Is the output reasonable compared to inputs? gES

9. Are the specified parts, equipmen-., an rocesses uitable for the application? yes specified materials compatible with each other and'he design

10. Are the environmental conditions to vhich the materials vill be exposeds ~

'~/I'ED Procedure 3.3/Rev. 50

11. Have adequate specified?

maintenance features and requirements been Page Document Type 2

.  !~ t'1

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 I&a been considered and resolved? 2 For each question on the check list not answered yes, explain belo~. If "Not Applicable" give reason.

Signature Date (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.

NEO Procedvre 3.3/Rev. 50

Design Package Mod. No. ~PC -6 47 Setpoint Worksheet Field Rev.

Page No.

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

Design Package Mod. No. PCR-6547 Setpoint Worksheet Field Rev. 0 Page No.

S-0 C- 03 TAG NUMBER INSTRUNENT SPAN 0-3000 PSIC SET POINT FUNCTION S/R POINT UNITS SET'OINT ACTIOH TOLERANCE 1 RCS PRESSURE ALT HINI-FLOU PERNISSIVE SET 2300 PSIC a15.0 INCR RESET 1750 PSIG a15.0 DECR SET RESET SET RESET SET RESET REFERENCE DOCUNEHTS AND NOTES PCR 6547 <<CS P ALTERNATE NINI FLOU CALCU AT OH HHP- INST-'1044 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 lVM. Na. KR-6547 Cov'er Sheet Field Rev. hb, 0 DESIGN DOCUMENTATION REVISIONS

Form 6 MOD NO. PCR-6547 DRAWING REVISION SHEET FIELD REVISION NO. 0 PAGE NO.

DRAWING- ': DRAWING UPDATE "RECORD OF NUMBER ":, TITLE BEFORE REVISION OPERA-

BILITY 2166-B-401, CVCS MINI-FLOW VALVE 2CS-V757SA-1 CWD NO S317 2166-B-401, CVCS MINI-FLOW VALVE 2CS-V759SB-1 CWD NO 8319 1364-46574, PZC CAB 1 INTERCONNECTING WIRING NO S22 1364-46577, PZC CAB 4 INTERCONNECTING WIRING NO S8 2166-S- RCS WIDE RANGE PRESSURE LOOP 3 NO PRC0402 2166-S- RCS WIDE RANGE PRESSURE LOOP 1 NO PRC0403 1364-1328, PROCESS CONTROL SYSTEM BLOCK DIAGRAM NO S29 1364-10929i NSSS PCE EXT CONNECTION DIAGRAM NO S2 1364-10929, NSSS PCE EXT CONNECTION DIAGRAM NO S5 1364-51840 PRINTED CIRCUIT CARD LIST CAB 1 NO 1364-92103 NSSS PIN ASSIGNMENTS NO 1364-51837 PRZNTED CIRCUIT CARD LIST CAB. 4 NO 1364-2776'26 SSPS-INTERCONNECTING DIAGRAM NO 1364-2776, SSPS-INTERCONNECTING DIAGRAM NO S28 1364-45841, SSPS-SCHEMATIC DIAGRAM NO S59 1364-45841, SSPS-SCHEMATIC DIAGRAM NO S58 1364-37747 SSPS OUTPUT CAB 2 WIRING LIST NO 1364-2776, SSPS-INTERCONNECTING DIAGRAM NO S30 1364-45841, SSPS SCHEMATIC DIAGRAM NO S49 1364-37746 SSPS OUTPUT CAB 1 WIRING LIST NO 2166-B-432 SHNPP INSTRUMENT LIST NO 2166-B-508 SHNPP SETPOINT DOCUMENT NO NPMP - REV. 4

Form 6 MOD NO+ PCR-6547 DRAWING REVISION SHEET FIELD REVISION NO. 0 PAGE NO.

."'RAWINGj~$$": UPDATE ~p> ;: ~RECORD 'OF';

"":-" "-NUMBER'~9i:;",i -.BEFORE Jr~REVISION ~~";:

,:OPERA-,wi

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

2166-S-2020 LIMITORQUE WIRING DIAGRAM NO S28

• For later use in tracking completion of the revision.

NPMP - REV. 4

Form 6 MOD NO.

DRAWING REVISION SHEET FIELD REVISION NO. 0

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

'UPDATE:i:::4 )g+RECORD","'OF/

BEFORE!.,> .kijREVISION'.'jj~

";

CBILITY~~e 2165-G-804 CVCS FLOW DIA. .YES 2165-S-1304 CVCS SFD YES 2165-G.805 CVCS FLOW DIA. YES 2165-S-1305 CVCS SFD YES 2165-G-140 CVCS RAB PLAN NO 2165.G-141 CVCS RAB SECTIONS NO 1364-96842 SI/CHARGING PUMPS MINI-FLOW STRAINER NO 1364-42815 MINI-FLOW ORIFICE ASS'Y NO 1364-B-069 SHNPP VALVE LIST NO 1364-B-070 SHNPP LINE LIST NO 1CS-650 SOUTHWEST FAB. ISO NO 1CS-651 NO II a II 1CS-150 NO II 1CS-151 N N NO II 1CS-152 N NO 2166-B- CABLE AND CONDUIT LIST NO 043S01 2166-G-322 RAB CONDUIT, TRAYS 6 GROUNDING EL. 305'HEET NO 1 UNIT 1 2166-S-2530 MEQ LIST NO MLA 2166-S-2530 MEQ LIST NO MLB 2166-S-2530 MEQ LIST NO 011'1 1-CS.H-4400 PIPE HANGER DRAWINGS NO 1-CS-H-4403 II II II NO 1-CS-H-'4406 NO 1-CS-H-4609 NO 1-CS-H-4610 tl II II NO 1364-93934 VOGT VENDOR DRAWING FOR 3/4" VALVES NO 2.l(p>-5-2><<Co~ ~n.~~ e Lc J e.l, G <'+

C rGQBg Vg ll/e 4 w<<P C ~ e NPMP - REV. 4

Form 7 MOD NO.

DESIGN DOCUMENT REVISION SHEET FIELD REVISION NO.

PAGE NO.

';:;:,DOCUMENT;,.",I:;,';"" UME UPDATE.i-"-', '-'OF

"'-+RECORD BEFORE~~, <'"IREVISION "

OPERA =."'~

'BIL'ITY 1-CS-H-4235 PIPE HANGER CALCULATION NO 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 N 1-CS.H-4241 1-CS-H-4237 1-CS-H-4239 1-CS-H-4609 1-CS-H-4610

• For later use in tracking completion of the revision.

NPMP - REV. 4

Form 7 MOD NO. 7 DESIGN DOCUMENT REVISION SHEET FIELD REVISION NO.

PAGE NO h

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

.j ":.REVISION

~~.'BEFORE

'OPERA-.;P>~

'.BIL'ITY.'," .

~~'-CS-H-4403 PIPE HANGER CALCULATION NO 1-CS-H-4406 1-CS-H-4400 1-CS-H-4420 141-1A PIPE STRESS CALCULATION 141-1 141-2 DAC-1 AUXILIARY SYSTEM LOAD STUDY NO E-6001 LOAD FACTOR STUDY FOR SHNPP NO

• CS-0021 MECH. ANAL. AND CALC. FOR 1CS-746 NO

• CS-0022 MECH. ANAL. AND CALC. FOR 1CS-752 NO DBD f104 SAFETY INJEJCTION SYSTEM DBD 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 BY CK hPPVD CP&L - NED - DRYING REVISION (5444MED ~ HNP)

~ ~

g)EC,B7'E /=go<

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

COMPONENT KVAl.UATION REPORT 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 tAOCE NOR~ NSIENT Q5h AtSIEMT $ tEFKAKNCK CONOITION ONTION CORDI TION CODE No, PNQkCTER TED'EIATUAE t Fal 130 104 3 ill 4 ++ 130 ISO'fC Llit VALVE LIST OWL

!NE 1

hB21-h, B 2-tltKSSUAE 2712 MLS h SW h

FShR g.)I.C 'AYH F5' 3.JJ. Q t PSIQ CHEICCALS

'IP 5-1 N/h, Fs~ 3.)le Table 1-2 AVIATION + f2 (+5)

I~ fllLll0 23 4+~89 I~ F!0 Lilt 23 l AADQ hB21"R4oR5 hB21-R4,R5

~AGENCY 8/h FSqg 3 /)B t FT)

OPERASILITV 10 YAS O'NL" 1 Yr, PSAR Section 1364-53215 CUAt.IFICaTtoM C08%NTQ Part 0 4 0 OOOO 0 0 0 0 0 0 0 0 0 OO A AN 0 0 0 0 0 0 0 0 04001 STATUS'E.VIS bio cAXF z~

ORB JJULJJl 0 e 0 0 000 OO OOOQOOO e Qo ~ FEE PA ED CKKD BYs 8'fs OATf s~~~~-85 Pggfg 1-30-85, 8-15-85

~~ gogS7 gt9S+ pb~E' 0 OOIOOOAOOOOOOOI o+/

CQBLF12 ME HAINTENAHCE ACTIVITIES 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 A/B ~

EDSS ~

PERIODIC/REPLACEMENT MAI Part Date ANCE:

CPAL Repla ment

~Deseri tion Part No. Int val Renarka I None Required 2 ~

3 ~

4 ~

Patch Tech Ra Dar.e C, MAINTENANCE CYCLE START DATE:

Fuel Load D/K. INSPECTION/REFURBISHHEHT RE EMENTS:

Hone Required Prepared: Date:

Revievcd: Date:

Approved:

g ~

• r Date: <</c/~

4 S

NR1-055

62 11-15 6 0004 MEQ-:i~>S-ML-A CHECKLIST 4 EBASCO TAG NO. CPbL TAG NO SYST EQU SPECIFIC IO HAN COMPONENT TYPE HQ0213 2CS-R521SN- I ICS-127 2060 FAU CS-R52 ISN MQ0109 2CS-R522SA- I BJS VCT RELIEF VLV ICS-290 2060 FAU CS-R522SA BJS JA CSIP SUCTION FROI4 RHR REL IE MQ0109 2CS-R52358- I ICS-293 2060 FAU CS-R52358 BJS 8 CSIP SUCTION FROM RHR RELIEF 9 C - 4 -I IC 20 ~Gjj C RELIEF L ld I 2 5- 75 I -744 060 FAU 5-R55

-R 8 -I N JS 1AR INQ 5

• HC-5 1l Qo I U EFUE WA R 5-755 206 AU CS-R 8SN 8 5 Gl L IN VA 12 2 2 5-VSO ISN- I lc - 7 200 BJ CVCS SSURIZE SPR R

L 13 HQ0024 2CS-V502SN-I ICS-492 2060 HNK CS-V502SN 14 MQ0024 2CS-V503SN- I ICS-480 TE'Ronj o6o INK CS-V503SN BJT BJT NORMAL CHARGING LINE I SOLAT ION ALTERNATE CHARGING LINE ISOLAT HQ0025 2CS-VS I ISA- I 15 ld MQ0025 2CS-V512SA- I ICS-7 ICS-B yg-5,-gpss AH 60 HOC CS-VS I ISA BJT CVC 5 NORM LTOW ORIFICE A CIV CS-V512SA I7 18 MQ0025 MQ002 I 2CS-V513SA- I 2CS-V514SN- I ICS-9 ICS-459 A~cR W5'gq oeo 2060

>i~oc HNK CS-VS'13SA CS-V514SN BJT BJT CVC 5 NORM LTDM ORIF ICE 8 CIV CVCS NORM LTDN ORIF ICE C CIV l9 BJT RCPS PI SEAL WATER BYPS ISOL V MQ0028 2CS-V515SN-I ICS-477 2060 llNZ CS-VS ISSN Bcc NORl4 CHARGING LINE CK VLV CLV 20 HQ0017 2CS-V516SA- I ICS-410 2060 INK CS-V516SA BBL RCP SEAL VTR RET INSIDE ISOL V 21 MQ0098 2CS-V51758- I ICS-472 2060 INK CS-V51756 BBL RCP SEAL VTR RET OU'TSIOE LSOL 21 HQ0085 2CS-V51858- I ICS-11 2060 HNK CS-VS IBSB BJT CVCS NORM LTON ISOL CIV 23 MQ0020 2CS-V519SN- I ICS-355 2060 CS-VS 19SM 1 INK 8JT A RCP PI SEAL WATER RETURN ISO 24 25 MQ0020 HQ0020 2CS-V520SM- I 2CS-V521SN- I ICS-396 ICS-437 2060 2060 INK HNK CS-V520SN CS-V521SN BJI BJT 8 RCP tj SEAL LEAKOFF LSOL VLV C RCP dj SEAL WATER RETURN ISO 28 HQO097 2CS-V52258- I ICS-34 1 2060 HNK CS-V52258 BBL RCP A SEAL INJECT ISOL VLV CIV 27 MQ0097 2CS-V52358- I ICS-382 2060 HNK CS-V52358 BBL RCP 8 SEAL INJECT ISOL VLV CLV 28 MQ0097 2CS-V52458- I ICS-423 2060 HNK CS-V52458 BBL RCP C SEAL INJECT ISOL VLV CIV 29 MQ0125 2CS-V541SN- I ICS-16 2060 HOG CS-V54 I SN Bcc REHT HX TCV INLET ISOL VLV 30 HQ0125 2CS-V542SN- I ICS-22 2060 jjoc C 5-V542SN Bcc REHT HX CV OUTLET ISOL VLV 31 MQ0125 2CS-V544SN- I ICS-31 2060 lloc CS-V544SN Bcc LO HX OUTLET ISOL VLV 31 MQ0125 2CS-V545SN- I ICS-35 2060 HOG CS-V545SN ecc INLET ISOL VLV TO LD PCV 33 MQ0125 2CS-V546SN- I ICS-43 2060 1 joe CS-V546SN Bcc OUTLET ISOL VLV TO LD PCV 34 HQ0127 2CS-V547SN- I I CS- 102 2060 INZ CS-V541SN Bcc DEMIN RETURN CK VLV 35 MQ0132 2CS-V552SN- I ICS-28 2060 lNI CS-V552SN BJT RHR FCV To LO HX 38 MOO 1 98 2CS-VSBOSN- I ICS-319 2060 HNZ CS-V580SN Bcc 5'V RETURN SPRAY To VCT CK VLV 37 MQ0202 2CS-V582SN- I ICS-123 2060 HMZ CS-V582SN Bcc Rc FLTR OUTLET CK VLV 38 MQ0199 2CS-V583SN-I ICS-167 2060 HNZ CS-V583SN Bcc VCT OUTLET CK VLV 39 HQ0139 2CS-V585SA- I ICS-214 2060 lloc CS-V585SA Bcc MINI FLOW ISOL VLV 40 1400108 ccS V58658-I ICS-278 2060 INK CS-V58658 BBL EMERG BORATLON FLOW ISOL VLV 41 HQ0107 2CS-V587SA- I ICS-110 2060 HOH C 5-V587SA Bcc A CSIP SUCTION X-CONN VLV 41 MQ0107 2CS-V58856- I ICS-168 2060 HOH CS-V58858 Bcc C CSIP SUCTIOM X-COMM WITH A C 43 MQ0 107 2CS-V589SA- I ICS-169 2060 HOH CS-V589SA Bcc C CSIP SUCTION X-COMM Vl TH 8 C 44 MQ0107 2CS-V59058- I ICS-171 2060 1IOH CS-V59058 Bcc 8 CSIP SUCTION X-CONN VLV 45 l400064 2CS-V591SA- I ICS-173 2060 Ho I CS-V59 ISA Bcc A CSIP SUCTION ISDL VLV 48 MQ0064 2CS-V592SAB- ICS-201 2060 llo I CS-V592SAB Bcc C CSIP SUCTION ISOL VLV 47 MQ0064 2CS-V59358- I ICS-187 2060 HO I CS-V59358 Bcc .8 CSLP SUCTION ISOL VLV 48 HQ0063 2CS-V594SA-I ICS-178 2060 CS Bcc A CSIP DISCH CK VLV 49 HQ0063 2CS-V595SAB- ICS-206 2060 V594SA'S-V595SAB Bcc C CSLP DISCH CK VLV 50 MQ0063 2CS-V59658-I ICS-192 2060 INZ CS-V59658 Bcc 8 CSIP DISH CK VLV 53 l400062 2CS-V591SA- I ICS- '183 2060 IIOK CS-V591SA Bcc A CS IP 0 I SCH I SOL VLV 51 MQ0062 2CS-V598SAB- I ICS-211 2060 llOK CS-V598SAB BCC C CSIP OISCH ISOL VLV 53 HQ0062 2CS-V59958- I IC5- 191 2060 IIOK CS-V59958 Bcc 8 CSIP DLSCH ISOL VLV 54 MQ0108 2CS-V60056- I ICS-182 2060 HOC CS-V60058 BBL A CSIP RECIRC LSOL VLV 55 HQ0108 2CS-V60158- I ICS-2 10 2060 HOC CS-V60 158 BBL C CSIP RECIRC ISOL VLV 58 57 MQ0108 MQ0115 2CS-V60258- I 2CS-V603SA- I ICS- 196 ICS-219 2060 HOL CS-V60258 BBL '8'SIP RECLR ISOL VLV 2060 llOH CS-V603SA Bcc A CSIP DISCH X-COMM VLV 58 MQ0115 2CS-V60458-I ICS-217 2060 HOH CS-V60458 Bcc C CSIP DISCH X-COMM VLV WI TH 1 59 MQOI IS 2CS-V605SA- I ICS-218 2060 l loll CS-V605SA Bcc C CSLP Dl SCH X-CONN VLV Vl IH 8 80 MQ0115 2CS-V60656- I ICS-220 2060 1 loll CS.V60658 Bcc 8 CSIP OISCH X-CONN VLV 70flM 0113 (OlldR

CAROLINA PUI LICHT COo SHEET 14 0 E)El ETE'Rc'r KbhSCO SERVICE',iCORPORATEO I

2/(o(u ~) N/ B SHEAROH IlARRIS NUCLEAR POMER PLAHT UNIT ECHAHICAL EQUIPHEHT (HOH-IK) QUALIPICATIOH (HEQ)

DEPT 530 M RA-(a5q7 HOH-HKTALLIC HATKRIAL PARTS LISTING (HSSS EOUIPHEHT)

HASTER LIST b CHECK LIST HO. VALVE/ UIPHKHT TAC HO. PART DESCRIPTIOH HATERIAL USAbLK LIPK I

7 y So iiii)e~ute rt DE'I.E/eu /0K'm-Clyde 3CS"t523SH Casket tlexltsllic 40 Packing cmin erv~ 40 Dis phrsgn bu ns rgPP 7 Ci See C~nt Porn b Transducer 25~@ See Co~nt tora b Alt'ilter Reg nest.g S

See C~nt Porn b tositioner e Convent tora b f@C / C'g-gyjr7 3CC-0277 SA D is ph'raga 'KPT 40 DIsphragn Support Sheet Polyurethane 4'1) 0 ging EPT 40 Casket KPT 40 Shia Masher Polyethylene See C~ent Porn b 114 3CC-bSSA tackiag C/sasr~~& 40 3CC-bl9SA bushing Stl v/TPE See C~nt tora 3CC-820Sb body Lioer KPT 40 3CC-8658 2CS-V603SA tacking a sass rag fn~ 40 2CS-V604Sb Casket 'tlexltailic 40 2CS-V6055A 2CS-V60658 3CS-V6825N Casket tlexltaIIIc 40 117 2CS-D633SN D le phrs go KPT 40 Dieph Supp Sht Polyurethane 4/0 Shin Masher Polyethylene See Co~nt tora b DRing EPT 40 118 2CS-V7575A Packing c AernwrvP 40 2CS-V7605A Casket t I ex its 1 I ic 40 2CS-V7SSSb 2CS-V75958 119 3CC-R135N Ho Hon-Hetsllic Parts 3CC-R12SH 120 3CS-V548SH Casket Plesltallic 40 3CS-V6SSSH 2526M

Design Package Mod. No. PCR-6547 Self-Assessment Records Field Rev. No. 0 Cover Sheet SELF-ASSESSMENT RECORDS

Form 17 ALARA PRE-DESIGN WALK-DOWN RECORD Plant HNP Project No. RET-P-6547 File No. RET-P-6 47 Mod. No. P R-6547 Revision 0 Mod. Title ALTERNATE MINlFL W REDESI N Scope of IVork This modification consists of removing 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 ALARA details to ensure a good engineered product.

Special ALARA Considerations

- wp@gQs (p orr, g rr Avv ~ uiu. HAiEnt urF'rcAuT RAOrArrcA Souci'-f pgsauTrrtl. foR 8zwe h cggb 7-Iilr pa0 ~uBsEQafAi

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~ RPrac gc,Be" s, <reui.b az Errors z~zwjg.I Y /br.rsHcD ~ PPGirEivT Barr.Our" ~F dR'uD,cR gati'-Tdc pr.r.rSH& To /'& AOE r4 SA'<~< Fcr.av c.r VFAcC PR&FABRrcRvrcN oF Qr.'u 5Hcrai.b Qe ~orrI si pE/Zf D rN 0'sr'lc riACZ ro Ass rsr Frrr D hKtetJ /

lAIS~~CAn od r~w~r r

5'4Qb i~g i'l( SC. Ac.Che.c3 +

If S~66 Lz i<WM GQr q~w~ ( ~

~&4~ n/&8 in/ Q ~IBM ~iCC-

/5 ~bm ~j~ r Ed William. P HP S~p~M r

) M8 C ha+ i c Q Design Engine.r Date Oc. <m PZ

>) 'Sc~~td S gee~+ W 5'4~<a',~ ALARA~ecpuist Date

<) Sl wc3b gM g~A I ee ~ ~) 7'"

) +$ 0%+5 ,

g 8 ~A.~Y~ c ~~% ~~s pc~+ c~$ Installation ~r.pr csentative 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 ~ Prevents pump damage due to introduction of foreign material that could plug mini>>flow orifices and dead-head pump.

2. Robinson event illustrates susceptibility in similar pump design.

3 ~ Cost is low.

4. Fabrication and installation will not extend outage window.

5. Strainer area is large relative to required flow there 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 crud potential hot spot(in low traffic area).

Permanent shielding can be installed at plant request.

DISCIPLINE DESIGN VERIFICATION RECORD Page 1

1. lnatrcatfcra to Verification Perscsnel Plant W 0 (Class A)

Project )0 [ ] Seiscscc (Class 6)

File Ho. Level [ ) FP-0 (Class 0)

Oocuaent Ho. Rev [ ) 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. Veri f1 cat i on Doccaaentati on Applicability Disci line 0 f sci l ine Hechanical [] Civil Structural []

HVAC [) Seismic Equip. Oual. []

Electrical [] Civil Stress [)

IIC M Fire Protection [)

Environnental Oualitication [)

Hcnan Factors [)

Haterfals [)

[]

Other []

Verification Hethods Used:

W Design Revfe<< [ ] Alternate Cafculat>ons [ ) Oualif fcation 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) Date Actfon taken makes Design Oocuccents Acceptable:

Design Veri f fec Date (OPE) Date HFD Procedure 3.3/Rev. 50

Page 1 DESIGN REVIEW CHECK SHEET P'lant Document Type Project Document No.

File 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 i ed?

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 Date (Design Verifier) gyp procedvre 3 3/<ev 50

DISCIPLE DESIGN VERIFICATION RECORD Page 1

l. Icmtnmti~ to Verification Persornel F'beah Plant + 0 (Class A)

Project ACf- 0 ( ) Seismic (Class 8)

File No. Level f ) FP-0 (Class 0)

Docunent No. >4-~R- f 5< Rev [ ) 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 Disci line Nechani eel [) Civil Structural I )

HVAC () Seismic Equip. 0uel ~ ()

Electrical Civil Stress (3 ICC (3 Fire Protection ()

Environeental Dualification Huren Factors I)

Haterials (3

()

Other ()

Verification Methods Used:

Pg Design Revie<< ( ) Alternate Calculations ( ) qualification testing Design Doom>>nt Acceptable,:

Design Verifier No ] )

SA

. cceo>>nts attached.

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

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

(RE) Oa'te Action taken makes Design Oocueents Acceptable:

Design Verifier (DPE) Date NED Procedure ~ ~~Re

Page 1 DESIGN REVIEW CHECK SHEET Plant Document Type Project Document No. - iVA-l 5z File 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: 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? ~cA o

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 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 Page 1

i. Itmtrta:ticks to Verification Persornet Plant AJP P4 Q (Ctass A)

Project ( ) Seismic (Class 8)

File Ko. Level ( ] FP-Q (Ctass 0)

Oocmeot No. Rev ( ) 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 (- Veri ficaticn Oon~tation

/

Appticability Oisci line Oisci line Nechani ca l Civil Structural ()

HVAC () Seismic Equip. Qual. ()

Electrical () Civil Stress ( )

)LC () Fire Protection ()

Environnentat Qualification ()

HLIaan Factors ()

Hateriats ()

()

Other ()

Verification Nethods Used:

Oesign Revie~ ( ) Alternate Calculations ( ) Qualification Testing

<es g No ( ) . cannents attached.

Oate Ackrxwtedgeaent of Ve ---' 'I 2.V/~Z (OPE)

(II. Resotuticn of Ccmaentst Ccaments Resolved (See Attached):

(RE) ~ Oate Acticn taken nekes Oesign Oocunents Acceptable:

Oesign Verifier Oate (OPE) Oate 3IRe eo NEO procedure 3

~ h ~ ' I <<I

)

J I ~

t ~ ~ r~

~ t /

P

~

I r P,<~J

/I k I ~

I ( i P

) r I ' ~

Page 1 DISCIPLINE TECHNICAL REVIEW of the COMPLETED DESIGN PACKAGE Plant 7= -4rl 7

[~ (Class A)

[ ) Seismic (Class 8)

Project Q File Ho. Ir Level [ ] FP-Q (Class 0)

Document Ho. Rev [ ) 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 i cable Applicable Disci line Yes Ho Initial Disci line Yes Ho Initial Mechanical [) [] Civil Structural [! (!

HVAC [) [) Seismic Equip. Qual. [) [)

Electrical [) [] Civil Stress [)

IKC [) [] Fire Protection [)

Enviroreental Qualification (! (!

Human Factors [) [)

Materials t! [!

Other [)

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

'. 3.

and proper?

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 [ ] - cottrnents attached.

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

(DPE) lr Resolution of Comnentst Caaments Resolved (See Attached):

(RE) Date Action taken makes Design Docunents Acceptaolet Discipline Tech Reviewer Date (OPE) Date Proc. 3.3 Rev. 40

Page -1 DISCIPLINE TECHNICAL REVIEW of the COMPLETED DESIGN PACKAGE Plant Project

[~ (Class A)

Seismic (Class 8)

Q [ )

File No. Level [ ), FP-Q (Class D)

Docunent No. Rev [ ) 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 Disci line Yes No Initial Disci line Yes No Initial Mechanical [) Civil Structural [) [)

HVAC [) () Seismic Equip. Qual. [) [)

Electrical [) [) Civil Stress [) [)

INC [), Fire Protection [) [)

Envirorax.ntal Qualification Hunan Factors [) [)

Materials [) [)

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 conpieted design package indicate that the transfer of design

'. 3.

information within your discipline has been accvrate, conplete and proper?

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?

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 'Not Appl icable, give reason. Initial those disciplines reviewed.

Complete Design Package Acceptable~ Yes, M rNo

.M [ ). - ctxnnents attached.

Discipline Tech ewe p'ev'I Date Acknowledgem~e t of Dlsciptsne %nn>~ Pgv~ wt Date - 2S-Resolution of Coamentst Comnents Resolved (See Attached):

(RE) Date Action taken makes Design Oocunents Acceptaole:

Discipline Tech Reviewer Date (DPE) Date Proc. 3.3 Rev. 40

Page 1 DISCIPLINE TEC][NICAL REVIEW of the COMPLETED DESIGN PACKAGE Plant '[WQ (Class A)

Project Q [ ) Seismic (Class 6]

File Ho. /I sl Level [ ) FP-Q (Class 0)

Document Ho. Rev [ ) Other Initial each Discipline or Area of expertise addressed by this Discipline Technical Review of the Completed Design Package and forward conpleted sheet to the I.ead Engineer. Related discipline reviews may be ccebined on one sheet.

Applicable Applicable Disci line Yes Ho Initial Disci line Yes Ho Initial Mechanical [ ) Civil Structural [] [)

HVAC [) [] Seismic Equip. Qual. [)

Electrical [) [) Civil Stress [] [)

IKC [) [] Fire Protection [) [)

Envirormenta[ Qualification JA []

Hunan Factors ( I Haterials [) [)

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

'. 3.

and proper?

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 icable,'ive reason. Initial those disciplines reviewed.

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

Date Acknowledgement of Discipline Technical Review:

(OPE) Date Resolution of Comnentst Cements Resolved (See Attached):

(RE) Date Action taken makes Design Ooctxnents Acceptaole:

Discipline 'Tech Reviewer Date (DPE] Date Proc. 3.3 Rev. 40

Page 2 DISCIPLINE TECHNICAL REVIEM CCHHEHT SHEET Plant Project File Ho.

Document Ho.

This sheet is only required when cccments are being made.

Conment Resolved Ho. Corrment Resolution Initial/gate dc u 64 Lc LC Proc. 3.3 Rev. 40

Page 1 DISCIPLINE TECHNICAL REVIEW of the COMPLETED DESIGN PACKAGE Plant [WQ (Class A)

Pro)eat Q [ ) Seismic (Class 8)

File Ho. Level [ ) FP.Q (Class O)

Document Ho. Rev 8 [ ) Other each Discipline or Area of expertise addressed by this Discipline Technical Revie~ of the Conp[eted Design package and forward co))pleted sheet to the Lead Engineer. Related discipline reviews may be combined on one sheet.

Init'nitial Applicable Applicable Disci line Yes uo Initial Disci line Yes Ho Mechanical C>v> l Structural [)

W)

HVAC E lee ISC tr ice l Seismic Equip. Qual.

Civil Stress Fire Protection 4))

)V')

Environnenta[ Qualification [)

Hunan Factors )~~

Materials Other l) l)

Mark each item yes, no, or not applicable and initial

1. 'ave design docunents or input from your each item checked by you.

discipline been properly interpreted and/or incorporated by other discipline? gag Does the ceryleted design package indicate that the transfer of design i 3.

information within your discipline has been accurate, coop[etc and proper?

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?

5. Are procedures in place to cover installation if step by step instructions were not provided? ~fC supporting disciplines or areas of expertise appropriately marked

're 6.

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) Date Resolution of Ccnmentst Coaments Resolved (See Attached):

(RE) Date Action taken makes Design Documents Acceptaole:

Discipline Tech Reviewer Date PE) Date Proc. 3.3 Rev. 40

Page 2 DISCIPLINE TECHMI CAL REVIEM COMMENT SHEET Plant Project File Mo.

Docunent Mo.

This sheet is only required shen caments are being made.

Comnent Resolved Mo. Conment Resolution Initial/Date Qv ESTIOiJ MoT h PLlcA L T 0' 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 [~ (Class A)

[ ) Se>sm>c (Class 8)

Project Q File No. I< Level [ ] FP Q (Class 0)

Docunent No. C4-4'6 +V Rev [ ) Other Initial each Discipline or Area of expertise addressed by this Discipline Technical Review of the Conpieted Design Package and forward conpleted sheet to the Lead Engineer. Related discipline reviews may be combined on one sheet.

Applicable Appl icable Disci line Yes No Initial Disci line Yes No Initial Mechanical HVAC

( ()/

Vd Civil Structural Seismic Equip. Qual.

t+l Electrical Civil Stress 18C Fire Protection Envirormental Qualification Hunan Factors Materials 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.

'etpiete For each question on the check list not answered yes, explain on page 2. If 'Not Applicable,'ive reason. Initial those disciplines reviewed.

Design Package Ac,~tablet YesI [.~ No

~ n ~

4 - conments attached.

Acknowl (DPE)

"~~

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

~

Date Date Resolution of Comnentst I

~

Ccm"..~tRes(lived gee (RE)

A(tac~).

Date 9+

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

Discipline Tech Review  ; Date

<OPE) Date Proc. 3.3 Rev. 40

Page 2 0 ISCIPLINE TECHNICAL REVIEM CCHHEHT SHEET Plant Project File No.

Document No. -'4 Rev This sheet is only required uhen contents are being made.

Conment Resolved No. Conment Resolution Initial/Date QE,s~~+ xm4cT wainmhzq &AoI;I.o ~<

- z 0 r 1)~

SE,C~oAI S>PeCZEcc ~IITheji~ /RENT RV 3 f SRoOLO ~f MS5ED IO QEFLKC+

+I'- AAlhM~ BQsII. I HK QOS~ !-or AVE. 4)g5 Q~fAf.O "to nm 6E. ~

Proc. 3.3 Rev. 40

le age ~

g of NED INTERDISCIPLINE REVIEW REQUEST (IRR)

IRR g'OD/RET/PCR/PCN g: Plane ~NP To: Unit/Subunit From: Unit/Subunit 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: Responsible Supervisor/Date: &4M Authorized Man-hours Charge Number e 'ZL/

MAPS Project No.: Activity:

'>>~

Phase:

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: Yea No e~ ff 'N'I'l

~

c-> c'~

Attachments (list): pY~ /J') g> ~/8/ i j> ply Responsible Supervisor/Date Actual Man-hours expended 0 Page 6 Rev. 4

I File Page ~~

g of NED INTERDISCIPLINE REVIEW REQUEST (IRR)

IRRt'lt'.

MOD/RET/PCR/PCNP To: Unit/Subunit PlantQQQ'HIS From.. Unit/Subunit Details of Review Request:

MODIFICATION WILL INVOLVE TEMPORARY REMOVAL OF SAFETY INJECTION PIPING FROM PENETRATIONS P415, P418, AND P426 WHILE INSTALLING STRAINERS.

PLEASE PROVIDE DESIGN INFORMATION.

/Z4.+ + 4, ~~7 RUSHtttt Response Required By:

Authorized Manhours Phase: Activity:

Response/Justif icati on 5Zt ~@ACR gO gg+6V p @AC Q g p B~

7'e" cF 7H+ /eSTAc-C~r/orJ QMAqg. VHK Sae~ckl ~R ]'k)+Q~IOQ vp'F'C.lE'v llv 7 Q/5 +g g ggpp~gg~c

~ ~gg gag~++

eggs

/M Z R/Z.Q 8 &Z8 l~ P/ft('g +~g~

Attachments (list):

Responsible " '

Supervisor/Dat =

Actual Man-hours expended Distribution:

NED GuidelineNo. E-24 Revision 3 (6/90)

gW '~p ile age ~

P ClV)L UNT 1 ~ f953 of NED PLINE REVIEW REQU To:

IRR y.

MOD/RET/PCR/PCN Unit/Subunit 0: Plant ~p~

From: Unit/Subunit 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.

Responsible Supervisor/Date: ~~

Authorized Man-hours Charge Number MAPS Project No.: 4 Phase: Activity:

Response/Justification:

Information Design Verified: Yes No (list):

~

Attachments Responsible Supervisor/Date / Actual Man-hours expended Dis tribution:

-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)

IRRg:

MOD/RET/PCR/PCNP P To: Unit/Subunit From: Unit/Subunit Details of Review Request: 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: 'Viz/>

Authorized Manhours Phase: Activity:

sponse/Justification:

4&o Aaa, l Wg c 7. /Z C. Ccd cu l ~ o~, XF Is renig 04 s' ~ ~ 0 c Fc ca+ o ~ ~ s i~ - oFF rs r'~~A'e~ aZ()

(eF4 t-(~4 L a<<~~c c a4 ~p~~, CdG ~

t-e F'~e if/ U lg c a(p aG ~

Attachments (li t):

Responsible Supervisor/Da e Actual Man-hours expended Distribution:

NED GuidelineNo. E-24 Revision 3 (6/90)

ile Page ~~

4 ng NED INTERDISCIPLINE REVIEW REQUEST (IRR) go~

J )ib ~l<~

IRRg:

MOD/RET/PCR/PCN8 Plant~

To eau Unit/Subunit From: Unxt/Subunit 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.

IP'S~ /+

j~p Pgwl

+~ A<p'cAeP'~ g Attachments (list):

Responsible Supervisor/Dat 7~ Actual Man-hours expended ~f < 'Y Distribution:

NED GuidelineNo. E-24 Revision 3 (6/90)

Page ~~ "

of 7

NED INTERDISCIPLINE REVIEW REQUEST (IRR)

(g97 I

~p/'/

j e

IRR jj'.

MOD/RRT/PCR/PCNP - Plant~

To: Unit/Subunit From: Unit/Subunit Details of Review Request:

PLEASE PROVIDE I&C SUPPORT FOR PCR 6530.

Responsible Supervisor/Date <////s~

Charge Number Phase: Activity:

esponse/Justification:

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

~M~M~~Hf~ -uaCo&~H ~-W-V'7 C/'uSPp'WW/'6W

/A Wur Attachments (list):

Responsible Supervisor/Date.. Actual Man-hours expended Distribution:

NED GuidelineNo. E-24 Revision 3 (6/90)

page ~~ of NED INTERDISCIPLINE REVIEW REQUEST (IRR)

Cp -o~ u~ S<lo)

MOD/RET/PCR/PCNg Plant HNP To: Unit/Subunit F rot. Unit/Subunit 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:

-'4 5 sponse/Justification:

Attachments (list):

Responsible Supervisor/Date ctual Man-hours expended B Distribution: 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 NED

~ )~~ J ~ ~ ~ ~

INTERDISCIPLINE REVIEW REQUEST (IRR) g i Jihad grot IRR8:

MOD/RET/PCR/PCNP Plant HNP To. Unit/Subunit From Unit/Subunit 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~S 4ua~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.

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

~~~ ~~~us.

Attachments (list):

CQ~ CH2. Abc. ~w6~%5 A6 CQf ~~a XwcAcT 9 ~ Ag~~ JQJALQAg~& foe'UtfLlhiib Auo 842lSM<'esponsible Supervisor/Dat lctual Man-hours expended Distribution:

NED GuidelineNo. E-24 Revision 3 (6/90)

ile g

/'i IL1Il NED INTERDISCIPLINE REVIEW REQUEST (IRR) p >(6 IRRg:

MOD/RET/PCR/PCN8'lant HNP To: Unit/Subunit From: Unit/Subunit E

Details of Review Request:

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

Responsible ~

Supervisor/Dat. Actual Man-hours expended Distribution:

)~jQ'L f-2) ~(Z.

NED GuidelineNo. E-24 Revision 3 (6/90)

File f age 1 of 33 NC. ATTACH.

CPIIL UNlT NED

,c93 INTERDISCZPLINE REVIEW RE{}UEST (IRR)

IRR g: HC-169 MOD/RET/PCR/PCN g: 6547 Plant HNP Too %t/Subunit SS CIV -SU ORTS Froi' unit/Subunit SS C V -S SS is form is used to rov ae nterd sc i e review docume tat o 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: Responsible Supervisor/Date Authorized Man-hours Charge Number MAPS Project No.: PCR-6547 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 CALCULATIONNUMBER HARRIS NUCLEAR PLANT 14 1-lA PCN/PID NUMBER PAOE REVISION PCR-6547 SUBIECT 0INATOR'S INITIALS/DATE SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF c.J

'S D/ITIALS/DATE VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

HANGER NO.CS- - 2 NODE PT.7 ISO NO. - 6- 8 SUPPORT SYSTEM CONDITION F, Fy F~ Ng l4I/

(LBS ) (LBS) (LBS) (FT-LBS) (FT-LBS) (FT-LBS)

DEADWEIGHT 2 ~ -217.

THERMAL I -132. 57.

THERMAL II THERMAL III PAD & TAD DBE SAM OBE(Inertia 44. 124.

DBE(Inertia) 70. 176.

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

DISPLACEMENTS x Y 5 (in) (in) (in)

THERMAL I 0. 00 0.00 0.0111 THERMAL ZZ

<ACCIDEÃD THERMAL ZZZ posf-Acc!DBIn NOTES: 1. +X ~ NORTH, +Y ~ UP, +5 ~ EAST.

2 ~

3 ~

CAROLINA POWER fi LIGHT COMPANY P CALCULATIONNUMBER LANI'ARRIS NUCLEAR PLANT 141-1A PCN/P JD NUMBER PAOE REVLSION PCR-6547 SlJBJECI'I OklQINATOR'S MTlALS/DATE CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF 9 7P-a~

VALVES REMOVED, FLOW ORIF ICES AND STRAINERS ADDED WITH LEAD BLANKETS.

HANGER NO.C 7 ISO NO. - - -68 SUPPORT SYSTEN CONDITION Fx Fy le (LBS) (LBS) (LBS) (FT-LBS) (FT LBS) (FT-LBS)

DEADWEIGHT -39.

THERMAL I -42.

THERMAL II THERMAL III PAD 6i TAD DBE SAM OBE Inertia) 76.

DBE(Inertia) 122 UPSET (+)

UPSET (-

'OS EMERGENCY(+)

EMERGENCY( )

DISPLACEMENTS Y 5 (in) (in)

THERMAL I 0.00 0.0098 -0.0475 THERMAL (AccIDEÃn II THERMAL

/)0$ f.ACCIDQG)

III NOTES! 1. +X > NORTH) +Y ~ UP, +5 < EAST

CAROLINA POWER R LIGHT COHPANY I'LANT CALCULATIONNUMBER HARRIS NUCLEAR PLANT 141-1A PCNJPID NUMBER RAOB REVISION PCR-6547 SUBJECT ORJOINATOR'S INITIALS/DATE SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF CHP~BI'S INITIAL TB VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS. ~tel '1~~

HANGER NO.CS-H-4233 ISO NO. A-236-CS-58 SUPPORT SYSTEM CONDITION r, Fv r, Ng Ny Nz (LBS) (LBS) (LBS) (FT-LBS) (FT-LBS) (FT-LBS)

DEADWEIGHT 44 -384.

THERMAL I '32.

-82 THERMAL II THERMAL III PAD 6 TAD DBE SAM '95.

OBE(Inertia 38.

DBE(Inertia) 61. 289.

UPSET (+)

UPSET (-) LnL) 1.

EMERGENCY(+) l55 EMERGENCY(-)

DISPLACENENTS x Y S (in) (in) (in)

THERMAL (NOLMAU I 0.00 0.00 -0.0520 THERMAL II THERMAL III NOTES: 1. +X a NORTH) +Y > UP( +Z a EAST.

2.

3.

CAROLINA POWER fi LIGHT COHPldpg PLANT CALCULATIONNVMBBR HARRIS NUCLEAR PLANT 141-1A PCN/PtD NVMBBR PAOB RBV!SION PCR-6547 SVBlECT ORIGINATOR'S MTlALS/DATE SI CHARGING PUMP ALTERNATE MINI-FLOW LINE/ RELIEF CHPXK1~JI'S INlTIALS/DATE VALVES REMOVED/ FLOW ORIFICES AND STRAINERS ADDED =

WITH LEAD BLANKETS. m)~( 11(l HANGER NO.CS-H-42 5 NODE PT.7163 ISO NO. - 36-CS 58 SUPPORT SYSTEN CONDITION Pv Ny Mz (LBS) (LBS) (LBS) (PT-LBS) (PT LBS) (PT-LBS)

DEADWEIGHT -166.

THERMAL I THERMAL II THERMAL III PAD 6 TAD DBE SAM OBE ( Inertia) 99.

DBE(Inertia) 166.

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

II(DAEDAL) DISPLACENENTS Y 5 (ia) (in)

THERMAL I 0.0275 0.00 -0.0723 THERMAL (ACCIDENT)

II THERMAL III posT Acc(DQfn NOTES: lo +X > NORTH'Y ~ UP( +Z > EAST+

2 ~

3 ~

CAROLINA PO%ER fi LIGHT COMPANY CALCULAI1ON NJMB BR HARRIS NUCLEAR PLANT 141-1A JAae RB'/LSIOH PCR-6547 SUBJBCT ORJOlNATOR'S MTIALS/DATB SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF 9-z3~z CHBCKBR'S DIJTIALS/DATB VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS. a/-. I HANGER NO.C - -4 68 NODE PT.7 ISO NO. - S-58 SUPPORT SYSTEX CONDITION rx r r, Nx (LBS) (LBS) (LBS) (rT-LBS) (rT-LBS) (rT-LBS)

DEADWEIGHT 21 ~ -104 THERMAL I 2 ~

'27

~

THERMAL II THERMAL IIZ PAD & TAD DBE SAM OBE(Inertia) 89. 75 DBE ( Inertia) 144. '29.

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-) KLc'l DZSPLACEMENTS x Y S (ia) (ia) (ia)

THERMAL (HOkllAU I 0.00 0.0152 0 F 00 THERMAL ZZ

<ACClDEVfl THERMAL III NOTES' +X NORTH( +Y ~ UPs +Z EAST 2 ~

3.

CAROLINA POWER fi LIGHT COMPANY CALCULATIONNUMBER HARRIS NUCLEAR PLANT 14 1-1A PAOE REVISION PCR-6547 SUBJECf SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF 3(" i ORIGINATOR'S INfflALS/DATE 9-z3-;z I

VALVES REMOVED ) FLOW ORI F CES AND STRAINERS ADDED CHECKER'S MTIALS/DATE WITH LEAD BLANKETS.

HANGER NO.C -H- ISO NO. - -C -5 SUPPORT SYSTEN CONDITION r, r, le Ny (LBS) (LBS) (LBS) (rT-LBS) (rT-LBS) (PT-LBS)

DEADWEIGHT -262. 63.

THERMAL I 80. -213.

THERMAL IZ THERMAL III PAD & TAD DBE SAM OBE ( Inertia) 108. 35.

DBE(Znertia) 187. 56.

UPSET (+)

UPSET -)

EMERGENCY(+)

EMERGENCY(-) Z.OLn DISPLACEMENTS X Y 5 (in) (in) (in)

THERMAL (NOkMAL)

I 0.00 0.00 0.00 THERMAL IZ (ACCQKNn THERMAL IZZ

()OSr ACC(na(TI NOTES 1 +X + NORTH) +Y + UP ) +2 + EAST 2.

3 ~

CAROLINA POKER fi LIGHT COXPANY PIAHT HARRIS NUCLEAR PLANT 141-1A PAOB REVISION PCR-6547 SUBJECT SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF gr',

ORIGINATOR'S INTTIALS/DATE CHECKER'S INITIALS/DATE VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

HANGER NO.CS- -4 7 ISO NO. 36- S-58 SUPPORT SYSTEM CONDITION r, Fy F, Ng (LBS) (LBS) (LBS) (FT-LBS) (FT-LBS) (FT-LBS)

DEADWEIGHT -81. -4.

THERMAL I 12 -17 ~

THERMAL II THERMAL III PAD 6 TAD

'5.

DBE SAM OBE(Inertia) 22 DBE(Inertia) 60. '6.

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

DISPIJlCI94l3lTS X Y 5 (in) (in) (ia)

THERMAL (HORllAU I 0.0324 0.00 0.00 THERMAL (ACCIDEÃl)

II THERMAL POST.ACCIDBÃn III NOTES: 1. +X ~ NORTH( +Y < UP( +5 < EAST.

2.

CAROLINA POKER & LIGHT COMPANY CALCULATIONNUMBER HARRIS NUCLEAR PLANT 141-1A PCN/PID NUMBER PAGE REVISION PCR-6547 SUBJECT ORIOINATOR'S INITIALS/DATE SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF C -z -a" CHECKER'S INITIALS/DATE VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS. H//M/8 I HANGER NO.CS- 29 ISO NO. - 6- S-58 SUPPORT SYSTEN CONDITION Fx Fy F~ Nz Ny (LBS) (LBS) (LBS) (FT LBS) (FT-LBS) (FT-LBS)

DEADWEIGHT -65. -4.

THERMAL I 10. 112.

THERMAL II THERMAL III PAD & TAD.

DBE SAM OBE(Inertia) 76. 89.

DBE(Znertia) 116. 132.

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

DISPLACENENTS Y

(in)

THERMAL

/MORNAY I 0.0572 0.00 0.00 THERMAL IZ "

THERMAL III POST.ACCIDENT)

NOTES: 1. +X NORTH, +Y UP, +2 EAST.

2 ~

3~

CAROLINA POSER fc LIQHT COMPANY CALCULATIONNUMBER HARRIS NUCLEAR PLANT 141-1A PAOE REVISION PCR-6547 SUBJECT ORIOINATOR'S INmALS/DATE SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF q.z~-a=

CHECKER'S INITI/QS/DATE VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS. s (>-s]S ~

HANGER NO. - -4 ISO NO.

SUPPORT SYSTEX CONDITION Px Fy r, )Ix My (LBS) (LBS ) (LBS) (PT-LBS) (FT-LBS) (FT-LBS)

DEADWEIGHT -9.

THERMAL I -34.

THERMAL II THERMAL III PAD & TAD DBE SAM OBE(Inertia) 442.

DBE ( Inertia) 657.

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

DISPLACENENTS X

(in) (in) (in)

THERMAL tNOXl4ALI I 0.00 0.0218 0.0244 THERMAL ZZ (ACClDe(n THERMAL 00$ T ACCQ)f&Q IZI NOTES: 1 +X > NORTH( +Y ~ UP, +Z < EAST.

2 ~

3 ~

C3EROLZNA POSER fc LIGHT COXPANY PLANT CALCUlATIONNUMBER HARRIS NUCLEAR PLANT 141-1A PAOE REVISION PCR-6547 SUBIECT ORIOINATOR'S INITIAL%DATE SI CHARGING PUMP ALTERNATE MIN I FLOW LINE( RELIEF ('

I

-Z~-'IZ.

CHECKPJI'S INITIALS(DATE VALVES REMOVED( FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS. P~. ~i.)3s~

HANGER NO.CS-H-4272 NODE PT.7760 ZSO NO. A-236-CS-59 SUPPORT SYSTKN CONDITION Fx Fy Fg lCy (LBS) (LBS ) (LBS) (FT-LBS) (FT-LBS) ( FT-LBS )

DEADWEIGHT -15.

THERMAL I 38.

THERMAL II THERMAL III PAD & TAD DBE SAM OBE Inertia) 85.

DBE(Inertia) 141.

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

DZSPLACEIQBITS X Y (in) (in) (in)

THERMAL I 0.0304 0.0044 0.00 THERMAL ZZ IACClDEY!)

THERMAL IZZ NOTESI 1 ~ +X > NORTH( +Y < UP( +2 > EAST 2~

3 ~

CAROLINA POWER fi LIGHT COMPANY PLANT CALCULATIONNUMBER HARRIS NUCLEAR PLANT 141-1A PCN/PID NUMBER I AOE RE I/ISIOIo PCR-6547 SUBIECf 0RIOINATOR'S INITIALS/DATE ING P~P ALTERNATE MINI-FLOW LINE RELIEF c.Q 5->swz.

CHECKER'S INITIALS/DATE VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS. P~ ~~5~

HANGER NO.CS- 6 ISO NO.

SUPPORT SYSTEM CONDITION Fr Fy F, Mg My M2 (LBS) (LBS) (LBS) (FT-LBS) (FT-LBS) (FT-LBS)

DEADWEIGHT -344.

THERMAL 2 22 ~

THERMAL II THERMAL IZI PAD & TAD DBE SAM OBE Inertia) 134.

DBE(Inertia) 223.

UPSET (+)

UPSET (-)

EMERGENCY +)

EMERGENCY(-)

DZSPLACEMENTS Y 5 (in) (in) (in)

THERMAL OIOlllAL)

I 0.0380 0.00 0.0135 THERMAL ZI IACCIDENT)

THERMAL iMST.ACCIDEÃn III NOTES: l. +X ~ NORTH, +Y a UP, +5 ~ EAST.

2 ~

3.

CAROLZM7L POSER 6 LZGHT COMPANY PLAINT CALCULATIONNUMBER HARRIS NUCLEAR PLANT 14 1-1A PAGE REVISIOH PCR-6547 SUBJECT 0RIOINATOR'S INITIALS/DATE SI CHARGING PUMP ALTERNATE MINI-FLOW L'INE RELIEF CHECKER'S INITIALS/DATE VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

HANGER NO.CS-H-4243 NODE PT.7790 ISO NO. -236-CS-59 SUPPORT SYSTEM CONDITION Fx Fy Ãz le (LBS) (LBS) (LBS) (FT-LBS) (FT-LBS) (FT-LBS)

DEADWEIGHT -245. 76.

THERMAL I 7 ~ -2 THERMAL IZ THERMAL IIZ PAD 6 TAD DBE SAM OBE(Znertia) 128. 77 DBE(Inertia) 223 '16.

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

DISPLACEMENTS x Y 5 (in) (in) (in)

THERMAL (HOAMAl)

I 0.0768 0.00 0.00 THERMAL (ACCUSANT)

II THERMAL POST ACCIDEÃQ IIZ NOTES: 1. +X < NORTH, +Y > UP/ +5 < EAST.

2 ~

3~

CAROLINA POWER fi LIGHT COMPANY PLANT CALCULATIONNUMBER HARRIS NUCLEAR PLANT 141-1A PCNIPJD NUMBER PAOE REVLSION PCR-6547 SlJBJECl'I ORlOlNATOR'S JNTIALSIDATE CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF 9, 'I-7~-eZ CHECKER'S JNJllALSIDATE VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS. P~. =l/<SPt HANGER NO. - 7 ISO NO. - S-SUPPORT 8YSTEN CONDITION FS Fy FB l4y (LBS) (LBS) (LBS) (FT-LBS) (FT-LBS)

DEADWEIGHT -68. 'FT-LBS)

THERMAL I -40.

THERMAL II THERMAL III PAD & TAD DBE SAM OBE(Inertia) 88.

DBE(Inertia) 143 UPSET (+)

UPSET -)

'EMERGENCY(+)

EMERGENCY(-)

DISPLACEMENTS x Y (in) (in)

THERMAL INOIMAQ I 0.0797 0.0085 0.00 THERMAL (ACCIDEYll II THERMAL posT.AccUKYn IZI NOTES: 1. +X > NORTH( +Y > UP( +2 > EAST.

2~

3 ~

CAROLINA POWER Cc LIGHT COXPANY CA~+Ox NUMEEa HARRIS NUCLEAR PLANT 141-1A PAGE REYlSIOH PCR-6547 SVBJECI'I OalalNA VOa S emu ~Am CHARGING PUMP ALTERNATE MINI-FLOW LINE) RELIEF c4 CHPLl<ER'S MTIALS/DATE VALVES REMOVED) FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

HANGER NO.CS-H-4261 ISO NO. A-236-CS-59 SUPPORT SYSTEX CONDITION rx r rg Nz Xy (LBS) (LBS) (LBS) (rT-LBS) (rT LBs) ( rT-LBS)

DEADWEIGHT -186.

THERMAL I -4.

THERMAL II THERMAL III PAD S TAD DBE SAM OBE Inertia 75 ~

DBE(Znertia) 126 UPSET (+)

UPSET ( )

EMERGENCY(+)

EMERGENCY(-)

DISPLACEMENTS x Y (in) (in) (in)

THERMAL I 0.0923 0. 00, -0.0261 THERMAL IZ (ACCDENT)

THERMAL IZZ POST.ACCDEÃE)

NOTES: 1. +X ~ NORTH, +Y > UP) +Z ~ EAST.

2 ~

3 ~

CAROLINA PO>ER  % LIGHT COMPANY PLANT CALCULATIONNUMBER HARRIS NUCLEAR PLANT 141-lA PAOB PCR-6547 SUBJECT ORIOINATOR'S INIALS/DATB SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF c.q g-">-'tz CHP~~JI'S INITIALS/DATB VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

HANGER NO. S- -4 47 NODE PT.7840 ISO NO ~ 6-SUPPORT SYSTEM CONDITION Pz Fv r, l4z llv (LBS) (LBS) (LBS) (PT-LBS) (PT-LBS) ( PT-LBS )

DEADWEIGHT -94.

THERMAL I 4 ~

THERMAL II THERMAL I I Z PAD & TAD DBE SAM OBE(Inertia) 52.

DBE(Inertia) 89.

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

DZSPLACEKENTS X Y 5 (in) (in) (in)

THERMAL (NORMA@

I 0.1368 0.00 -0.0970 THERMAL ZZ (ACCIDEtC)

THERMAL ZIZ NOTES: l. +X > NORTH'Y < UP( +Z a EAST.

2.

3 ~

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

$ UBJECT ORIGINATOR'$ INITIALS/DATE SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF Ql CHECKER'$ INITIAL$/DATE VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED

~,C WITH LEAD BLANKETS. I I

HANGER NO.CS-H-4 NODE PT.7 ISO NO. 6- S-59 SUPPORT SYSTEM CONDITION rx r r, Nx Ny (LBS) (LBS) (LBS) (FT-LBS) (FT-LBS) (FT-LBS)

DEADWEIGHT -68.

THERMAL I -112.

THERMAL II THERMAL IZ I PAD 6 TAD DBE SAM OBE(Znertia) 32. 24.

DBE (Inertia) 56. 37 UPSET (+)

UPSET (-)

EMERGENCY +

EMERGENCY(-)

DZSPLACEMENTS Y 5 (in) (in)

THERMAL (HOkNAL)

I 0.1838 0.00 0.00 THERMAL II THERMAL IIZ I)OST-ACCKIEI)TI NOTESI 1 +X ~ NORTH) +Y ~ UP) +5 ~ EAST'.

3 ~

CAROLINA POWER & LIGHT COMPANY euZULATIOa WISER IS NUCLEAR PLANT 141-1A PCNlPID NUMBER PAOE REVISIOH PCR-6547 SUBJECT ORIODIATOR S MTIALSlDATE iS I CHARGING PUMP ALTERNATE MIN I FLOW LINE ~ RELI EF CHECKER'S MTIALS/DATE VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS. n)~~~ ~

HANGER NO. -4 66 NODE PT.7 ISO NO. - S-5 SUPPORT SYSTEX CONDITION Fx Fy Fg Nx le Nz (LBS) (LBS) (LBS) (FT-LBS) (FT-LBS) ( FT-LBS )

DEADWEIGHT -49.

THERMAL I THERMAL II THERMAL IIZ PAD & TAD DBE SAM OBE(Inertia) 24.

DBE(Inertia) 41.

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

DISPLACEMIKTS Y 5 (in) (in)

THERMAL OIOkMAQ I 0.2109 0.00 -0.0751 THERMAL IZ (ACCIDEÃA THERMAL IZZ (TOST-ACCDENn NOTES: 1 ~ +X ~ NORTH, +Y ~ UP, +5 < EAST 2 ~

3 ~

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

HANGER NO.CS- 7

• RUOISO NO. - -C -5 SUPPORT SYSTEM CONDITION Fg Fy Ny Xg (LBS) (LBS) (LBS) (FT-LBS) (FT-LBS) (FT LBS)

DEADWEIGHT -39 THERMAL I 201. '11 THERMAL II THERMAL III

'5 PAD & TAD DBE SAM OBE(Inertia) 12.

DBE(Inertia)

'6 18.

UPSET (+)

UPSET -)

EMERGENCY(+)

EMERGENCY(-)

DISPLACEMENTS X Y 5 (in) (in) (in)

THERMAL (MORWAL)

I 0.00 0.00 -0.0398 THERMAL IACCIDEYf)

II THERMAL III lMST.ACCIDEYn NOTES: l. +X ~ NORTH'Y ~ UP, +5 ~ EAST.

2 ~

3~

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

HANGER NO.CS- - 59 NODE PT. ISO NO. - - -59 SUPPORT SYSTEM CONDITION r~ rz lly (LBS ) (LBS) (LBS) (FT-LBS ) (FT-LBS) (FT-LBS)

DEADWEIGHT -63.

THERMAL I -98. 54.

THERMAL II THERMAL III PAD & TAD DBE SAM OBE(Inertia) 15. 25.

DBE(Inertia) 24 44 UPSET (+)

UPSET -)

EMERGENCY(+)

EMERGENCY(-)

DZSPLACENENTS X Y S (in) (in) (in)

THERMAL (NOkMAL)

I 0.00 0.00 -0.0116 THERMAL ZZ IACCIDEHTl THERMAL oosT Acc/DEYn IZI NOTES: 1. +X ~ NORTH, +Y ~ UP, +Z ~ EAST.

3.

CAROLINA POWER ~ LIGHT COMPANY PLANT CALCULATIONNUMBER HARRIS NUCLEAR PLANT 141-1A PCN/PID NUMBER PAOE REVISION PCR-6547 SUBJECI'I ORIOINATOR'S INITIALS/DATE CHARGING PUMP ALTERNATE MINE-FLOW LINE, RELIEF P3 a~

CHECKER'S INITIALS/l)ATE VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS.

HANGER NO.CS- -4 5 ISO NO >> 6-CS- 9 SUPPORT SYSTEN CONDITION Px Fy r~ N)

(LBS) (LBS) (LBS) (PT-LBS) (FT-LBS) (tT-LBS)

DEADWEIGHT -30.

THERMAL I 185. -10.

THERMAL IZ THERMAL III PAD Ec TAD DBE SAM OBE(Ine).tia) 49. 19 DBE(Inertia) 72.

'1.

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

DZSPLACEMENTS X Y 5 (in) (in) (in)

THERMAL 0/OkMAL)

I 0.00 0.00 -0.0457 THERMAL (ACC)DEYn II THERMAL III

/)0$ f.ACCIDD)n NOTES! 1 +X ~ NORTH) +Y ~ UP) +Z > EAST.

3 2 ~

3 ~

CAROLINA PONE+ fg LIGHT COlCP7LNY PLANT HARRIS NUCLEAR PLANT 141-1A PCN/PID NllMBBR PAOB RBVLSION PCR-6547 SUBJBCI'I ORIOINATOR'S INITIALS/DATB CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF 0 ~

CHPXKFJI'S INITIALS/DATB VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS. Q a(~s)%'~

HANGER NO.CS-H-4253 ISO NO. A-236-CS-59 SUPPORT SYSTEX CONDITION r, Fy rz le le le (LBS) (LBS) (LBS) (FT-LBS) ( FT-LBS) (FT-LBS)

DEADWEIGHT 72 ~

THERMAL I -180. 43 THERMAL II THERMAL III '9 PAD & TAD DBE SAM OBE(Inertia) 36.

DBE(Inertia)

'0.

53.

UPSET (+) 401 UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

DISPLACENENTS X Y (in) (in)

THERMAL OIOM4ALl I 0.00 0.00 -0.0133 THERMAL IZ

{ACCUSANT)

THERMAL- ZIZ NOTES: 1. +X ~ NORTH/ +Y ~ UP( +Z < EAST.

2 ~

3 ~

CAROLINA XOWZR a LIGHT COXXmx PLANT CALCULATIONNl/MBER HARRIS NUCLEAR PLANT 141-'

PCN/PID NUMBER PAOE PCR-6547 SUBJECT 0RIOINATOR'S INITIALS/DATE SI CHARGING PUMP ALTERNATE MINI-FLOW LINE) RELIEF 8-"3-'l~

CHECKER'S INITIALS/DATE VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS. ~]~ IIC ~

HANGER NO.CS- -4 4 ZSO NO. CS-59 SUPPORT SYSTEM CONDITION Fx F~ le le Nz (LBS) (LBS) (LBS) (FT-LBS) (FT-LBS) (FT-LBS)

DEADWEIGHT -171.

THERMAL I THERMAL II THERMAL III PAD & TAD DBE SAM OBE(Inertia) 74.

DBE(Inertia) 122.

UPSET (+)

UPSET -)

EMERGENCY(+)

EMERGENCY(-)

DZSPLACEXENTS Y 5 (in) (in)

THERMAL (NOkMALl I 0.1084 0.00 -0.0860 THERMAL ZZ (ACCIDEÃn THERMAL ZZZ

@Off-ACCJDE)n NOTES'. +X ~ NORTH) +Y ~ UP) +5 < EAST.

3.

ClQtOLZMA POWER fa LIGHT COXPAÃY PLANT HARRIS NUCLEAR PLANT 141-1A PCg/PID NUMBER FAOE REVISION PCR-6547 SUBJECT ORJONATOR'S INITIALS/DATE SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF c.g q-zs-~z CHECKER'S INITIALS/DAYE VALVES REMOVED) FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS. p~

HANGER NO.CS- -4 45 NODE PT.84 ISO NO. CS-59 SUPPORT SYSTEX CONDITION Fx Fy Nx le (LBS) (LBS) (LBS) (FT LBS) (FT-LBS) ( FT-LBS )

DEADWEIGHT -89 THERMAL I -53.

THERMAL II THERMAL III PAD SI TAD '5.

DBE SAM OBE(Inertia) 34.

DBE(Inertia) 58. 50.

UPSET (+)

UPSET (-) 53 ~

EMERGENCY(+) Boa EMERGENCY(-) 10$

DISPLACENQPZS Y S (in) (in) (in)

THERMAL (NOLWALI I 0.0443 0.00 0.00 THERMAL IACCDEÃn II THERMAL III (POST ACCIDEÃTI NOTES: 1. +X > NORTH( +Y ~ UP) +Z ~ EAST.

2 ~

3 ~

CAROL INA llOÃER fi LIGHT COHP ANY PLANT HARRIS NUCLEAR PLANT 141-1A pCN/FG) NL.ABER PAOE PCR-654'7 SVBJECr ORlONATOR'S lNIALS/DATE SI CHARGING PUKP ALTERNATE MINI-FLOW LINE, RELIEF c-0 R-~-qz.

CHECKER'5 MTIALS/DATE VALVES REMOVED/ FLOW ORIFICES AND STRAINERS ADDED ~)wsP~

WITH LEAD BLANKETS.

HANGER NO.CS-- ISO NO. -5 SUPPORT SYSTEM CONDITION rx r le Ny Xz (LBS) (LBS) (LBS) (FT-LBS) (FT-LBS) (FT-LBS)

DEADWEIGHT THERMAL THERMAL THERMAL PAD & TAD DBE SAM I

II III 37 2

'z

~

~

OBE(Inertia) 32

'3 DBE(Inertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

DI SPLACEMENTS x Y (in) (in) (in)

THERMAL OlOlQlALl I -0.0127 0.00 -0.0641 THERMAL II THERMAL posT.AcclDExn III NOTES 1 +X + NORTH'Y + UPg +Z + EAST 2 ~

3~

CAROLINA POWER fa LIGHT COMPANY HARRIS NUCLEAR PLANT 141-1A PCN/FID NUMBER I'A0E REVISION PCR-6547 SUBJECT ORIOINATOR'S INITIALS/DATE SI CHARGING PUMP ALTERNATE MINI-FLOW LINE/ RELIEF C 9- ~~z.

CIKCKER'S MTIALS/DATE VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS. l> 3s HANGER NO.CS-H-4237 NODE PT.8460 ISO NO. 1A-236-CS-59 SUPPORT SYSTBX CONDITION Fg r Fg lCy (LBS) (LBS ) (LBS) (FT-LBS) (FT-LBS) ( FT-LBS )

DEADWEIGHT -66.

THERMAL I 32 ~ -4.

THERMAL II THERMAL III PAD & TAD DBE SAM OBE(Inertia) 39. 36.

DBE(Inertia) 56. 56.

UPSET (+)

UPSET (-)

EMERGENCY(+) fz(

EMERGENCY(-) )

2'I SPLACEMENTS Y 5 (in) (in)

THERMAL (NOkMAU I 0.00 0.00 -0.0454 THERMAL

{ACCIDENT)

II THERMAL ZZZ POSI'ACCIDENT)

NOTES l +X ~ NORTH@ +Y ~ UP g +Z ~ EAST 2 ~

3.

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

CHECKER'S INITIALS/DATE WITH LEAD

~l~1'ANGER NO.CS-H-4 39 NODE PT.7730 ISO NO. CS-59 SUPPORT SYSTEN CONDITION rx r~ Ny (LBS ) (LBS) (LBS) (FT-LBS) (FT-LBS) (FT-LBS)

DEADWEIGHT -134.

THERMAL I -14.

THERMAL II THERMAL III PAD 6 TAD DBE SAM OBE(Inertia) 93.

DBE(Inertia) 143.

UPSET (+)

UPSET -)

EMERGENCY(+)

EMERGENCY(-)

24'ISPLACEMENTS Y 5 (in) (in)

THERMAL INOkMALI I 0.0086 0.00 0.0296 THERMAL II THERMAL III (10'CClDENT)

NOTES 1 +X a NORTH( +Y a UP) +5 ~ EAST 3.

CAROLINA POSER fc LIGHT COMPANY HARRIS NUCLEAR PLANT 141-1A PCN/PID NUMBER PAOE REVISION PCR-6547 SUBJECT ORIGINATOR'S INITIALS/DATE SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF CHECKER'S D/ITIALS/DATE VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS. g . ~ij~lR~

HANGER NO. ISO NO. -C SUPPORT SYSTEX "

CONDITION Fz Fy llz lip (LBS) (LBS ) (LBS) (FT-LBS) (FT-LBS) (FT LBS)

DEADWEIGHT -10. -1.

THERMAL I -6. 7 ~

THERMAL II THERMAL III PAD & TAD DBE SAM OBE(Inertia) 4 ~ 2~

DBE ( Inertia) 7~ 4.

UPSET (+) 20. 8.

UPSET (- 20. 8.

EMERGENCY +) 23. 10.

EMERGENCY(-) 23 10.

D IS PLACEKENTS

~ I (in)

Y (in) 5 (in)

THERMAL P(OkWAll I 0.00 0.00 0.00 (A~ II THERMAL THERMAL III POST ACCRDfTI NOTES: 1. +X > NORTH, +Y ~ UP( +Z ~ EAST.

2 ~

3 ~

ChROLINh POKER & LIGHT CONPhNY P1AHT HARRIS NUCLEAR PLANT 14 1-lA PCN/PID NUMEER PAOE REVISION PCR-6547 SUBJECT ORIOINATOR'9 INITIALS/DATE SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF Ol- ZS-eZ, CHECKER'S INITIALS/DATE VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED LEAD BLANKETS. 'ITH ISO NO. A- 36-CS-58 SUPPORT SYSTEX CONDZTION Fy F~ Ng (LBS) (LBS) (LBS) (FT LBS) (FT-LBS) ( FT-LBS )

DEADWEIGHT -13 -1 ~

THERMAL I '6.

THERMAL II THERMAL IZZ PAD & TAD DBE SAM OBE(Inertia) 12. 36.

DBE(Inertia) 20. 53.

UPSET (+) 31. 37

'7 UPSET (-) 31.

'4.

EMERGENCY(+) 39.

EMERGENCY(-) 39. 54.

DZSPLACENE)lTS X Y 5 (in) (in) (in)

THERMAL Z 0.00 0.00 0.00 QIORMAII THERMAL IZ ~

THERMAL ZZI EST.ACCDEYn NOTES: 1. +X a NORTH( +Y a UP) +Z ~ EAST.

2 ~

3 ~

CAROLINA POWER 4 LIGHT COHPAHY HARRIS NUCLEAR PLANT 141-1A PCN/PID NUMBER PAOE REYISIOtt PCR-6547 SUBJECT ORIGINATOR'S MTIALSJDATE SI CHARGING PUMP ALTERNATE MINI-FLOW LINE RELIEF C-.', ~.-'3~=.

CHECKER'S MTIALS/DATE VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS. 9~ a) )3(~

La~a,w<D 'Loam F(Lo~ ('I 's. iui- L(s ) Hi.-2 A~o ).4L. Z..

HANGER NO.CS- -4403 NODE PT. ZSO NO. - 6- S-59 SUPPORT SYSTEN CONDITION F, F FR Ng l4y (LBS ) (LBS) (LBS) (FT-LBS) (FT-LBS) (FT-LBS) 5l -7 DEADWEIGHT -406.

ILn 2 ~ l. 26.

THERMAL I LuLo 104. -35.

-L lI 5j -2.>

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

THERMAL cl IIIo~ I.iS)- HS ~bb:~s)= Bo ~h..uS3=2.bh II'l (I~3.- 5 RS (i.to5~=

(

PAD 6 TAD DBE SAM OBE(Inertia) 86.

ll162. 2.7.

159.

l 5'l 'l5 101.

50 Lo

92. 45.

41 55 H Zws S-l 'l4 Ol 1o l DBE(Inertia) 138. 2 ~ 258. 161. 141. 72.

UPSET (+) 05 UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

DZ SPLACENENTS Me,<uC.C, (S,~~< Zoaco.

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

Z Y 5 ( a4',QL. l Ou LK Bl-S 0 l'~Zev THERMAL I 0.00 (in) (in) 0.00 0.00 (in) LR<l l4 T. ha 9 5 BS 2 lZ:s I e.v.

(NakMALl THERMAL ZI 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 PACE REVISION PCR-6547 SUBJBCf ORIOINATOR'S INITIALS/DATE SI CHARGING PUMP ALTERNATE MINI-FLOW LINE RELIEF cA 9-z~~~

CHECKER'S D/ITIALS/DATE VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS. Ili g.~'~,

Loea=u.c n Loans Fe.oe. C ops. lHl-LO L.Hl- l 4e -

HANGER NO.CS-H-4406 ISO NO. 3 -CS-59 SUPPORT SYSTEX CONDITION Fx Fy Fg Xg Ng (LBS) (LBS) (LBS) (FT-LBS) (FT-LBS) (FT-LBS)

Sl 5 SL ZO DEADWEIGHT -406. -24.

ml so% Zh -5 5H -5% Zlo sm THERMAL I 7 ~ -45. 83. 17. -25. -48.

THERMAL II 'LOI 9 MCt %lg\I

%THERMAL

~

III ~7, . 'lip)%

PAD 6 TAD DBE SAM Z.S I to'E SL OBE(Inertia) 84. 161. 100. 54. 27. 43 5h Ih 300 IO 136. 285. 173. 93. 47. 70. 'BE(Inertia)

UPSET (+)

UPSET (-)

EMERGENCY(+)

EMERGENCY(-)

DISPLACE)69iTS Lo as~~c Q~~c ( oac~

CAu: l%L.N Ou W.ZSR~ > 0"L I'Os 5

t au'H'L-L. Ow L".EI. bi ~~ 4I5S v m (in) Col.c.: LSL Z Ow 6-Ih-5K 2. 'O'.Yl V.W THERMAL 0/0kNAQ I 0.00 0.00 0.00 THERMAL (ACCQKIVQ II THERMAL III POST.ACC!DENT)

NOTES: 1. +X ~ NORTH, +Y ~ UP, +Z ~ EAST.

3.

CAROLINA PONER a LIGHT COMPANY HARRIS NUCLEAR PLANT 141-1A

~/PID NUMBER I'AOE REl/IS IOH PCR-6547 SUBJECT ORIONATOR'S MTIALS/DATE SI CHARGING PUMP ALTERNATE MINI-FLOW LINE, RELIEF ( 4 e-~~-~

CHECKER'S MYI/CS/DATE VALVES REMOVED, FLOW ORIFICES AND STRAINERS ADDED WITH LEAD BLANKETS ~ C1) l ) )S~

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

HANGER NO. NODE PT. ISO NO.

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

SUPPORT SYSTEX CONDITION Fy F, Ng Ny Ng (LBS) (LBS) (LBS) (FT-LBS) (FT LBS) (FT-LBS) 0 -q5 ~l z. G 2. 0 IC)

DEADWEIGHT 2 ~ -364. 53. 43. 46. -21.

THERMAL I 93. -42.

-ll -S 445.

~l 284. L'I 5 318.

P1

-36.

THERMAL II (%.l Kl.t'uhi %L.~

~ HERMAL III l4crc 1 lq,5'b.l.SN= Z, l 5~(i.l))N=QQ SCCA.ml~ hM 2Mb. cA:'L& I ~DPI -~l Al),l PAD C) TAD DBE SAM 1 '\+5 ~ \

OBE(Inertia) 84. 167. 284. 212. 214. 74.

VS 2.'1 le L1 2n5 lQ DBE ( Inertia) 135. 290. 413. 303. 302. 110.

UPSET (+) B~z ( 5CI UPSET (-)

EMERGENCY(+) OO I OL "I EMERGENCY(-) 3QI I DZSPLACEMENTS C.OMfhS.llC.O A~~C- LORQbl Y 5 C.a~'si-ia ou al.aolz. > W':o<

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

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

THERMAL 0/0kMAl)

I 0.00 0.00 0.00 THERMAL ZZ IACClDEYn THERMAL ZZZ nfl'ACCIDEYn NOTES: 1. +X > NORTH) +Y > UP) +5 < EAST.

3.

C dC Mr r p ~l

g. 5W P ~ W~mn c. f= 5/W J

/I S/= = CMw 8 8W C'o Ad -+J- ods z ohio y 9b

Page'~ of ~ NED INTERDISCIPLINE REVIEW REQUEST (IRR)

IRRg:

MOD/RET/PCR/PCNO P lant'~

To: Unit/Subunit From:. Unit/Subunit 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 Phase: Activity:

esponse/Justification: AERY?

/<re <~c>A 5g g/d, >y A&y.~g gree++ ~w g1~H. +Row '51 re ~

~s g- >~ ~~ 4> Ps>p~

yV~ /~f 7- g-rod@ Au / ~ 5 =Md Attachments (list): 5P.- C-/uc C S4r~~ ~ 4 S+~Cg Responsible Supervisor/Date

/r,~Actual Man-hours a.xpended I

Distribution:

NED GuidelineNo. E-24 Revision 3 (6/90)