Text

To Calculation No. PNPS-1-ERHS-II.B-4, Control Room and Technical Support Center Accident X/Qs Using ARCON96, Attachment 3 to 2.04.003
	ML041130107
Person / Time
Site:	Pilgrim
Issue date:	04/14/2004
From:	Balduzzi M; Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	2.04.003 PNPS-1-ERHS-II.B-4, Rev 1
	Download: ML041130107 (78)
	v • d • e

Attachment 3 to 2.04.003 Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Plant Proposed Amendment to the Technical Specifications Entergy Calculation No. PNPS-1-ERHS-II.B-4, Rev. 1, "Control Room and Technical Support Center Accident X/Qs Using ARCON96" (49 pages).

1

Alllab -

I 7A-'n terg y CALCULATION COVER PAGE RType B4.01 LInP-2 EJIP-3 OIJAF

[DPNPS EjVY Calculation No. PNPS-1-ERHS-II.B-4 This revision incorporates the following MERLIN DRNs or Minor Calc Changes:

Sheet I of 43

Title:

Q Control Room and Technical SuDPort Center Accident y/O's Using z QR ARCON96 NQR Design Basis Calculation?

Discipline: Systems and Safetv Analysis DYes s C No This calculation supercedesvoids calculation: ERHS-II3.B-4. Revision 0 Modification No./Task No/ER No: N/A 0

No software used I]

Software used and filed separately (Include Computer Run Summary Sheet). If "YES', Code 0

Software used and filed with this calculation. If "YES", Code: ARCON96 System NoJName: N/A Component No./Name: N/A (Attached additional pages if necessary)

Print / Sign STATUS OTHER REV #

PendA, PREPARER REVEWERIDESIGN DESIGN APPROVER DATE V, S)

VERIFIER P. Compagnone P. T. Karatzas S. Wollman I

A5

___ma

CALCULATION SHEET CALC NO. PNPS-I-ERHS-II.B-4 Revision I

Entergy Sheet 2 of 43.

SUBJECT:

Control Room and Technical Support Center Accident 7/0's Using ARCON96 RECORD OF REVISIONS Calculation No.

PNPS-IERHS-II.B-4 Revision No.

Description of Change Reason For Change 0

New calculation 1

Full revision Addition of new release location; correction of release height input for 2 other release locations

_____________________________________________________ I

____________________________I_______________I_______

CALCULATION SHEET CALC NO. PNPS-l-ERHS-II.B-4 Revision I

Entergy Sheet 3 of 43.

SUBJECT:

Control Room and Technical Support Center Accident iIO's Using ARCON96 CALCULATION

SUMMARY

PAGE Page 1 of 1 Calculation No.

PNPS-1-ERHS-H.B-4 Revision No.

1 CALCULATION OBJECTIVE: To determine the atmospheric dispersion factors (X/Q's) to the Control Room and Technical Support Center using the ARCON96 computer program and 5 years of meteorological data.

CONCLUSIONS: The atmospheric dispersion factors are as follows:

To

=*

Control Room [Table 8-1]

From =>

Main Stack Turbine Bldg.

TB RFP Reactor Bldg.

Reactor Bldg.

Area I

Vent T. ':k1ock Time Interval (s/rm')

(sNW -

s/mI) t (s/mn (s, lita 0-2 hrs 7.32E-07 3.44E-03 2.04E-03 1.85E-03 9.87E-04 2 - 8 hrs 4.93E-07 2.79E-03 1.70E-03 1.45E-03 7.39E-04 8 -24 hrs 9.98E-08 1.05E-03 5.95E-04 5.19E-04 2.71E-04 1 - 4 days 1.06E-07 8.86E-04 5.16E-04 4.21E-04 1.86E-04 4 -30 days 8.95E-08 7.82E-04 4.64E-04 3.8 IE-04 1.58E-04 To

=

Technical Support Center [Table 8-2]

l From rn Main Stack Turbine Bldg.

TB RFP Reactor Bldg.

Reactor Bldg.

Area Vent Trucklock Time Interval (s/m3)

(s/m)

(slr')

(s/e)

(slmr) 0-2 hrs 9.23E-07 1.711E-03 7.99E-04 7.26E-04 4.34E-04 2 - 8 hrs 6.34E-07 1.44E-03 6.37E-04 5.61E-04 3.34E-04 8 - 24 hrs 1.3 IE-07 5.09E-04 2.29E-04 1.98E-04 1.24E-04 1 -4 days 1.37E-07 4.5 IE-04 1.84E-04 1.60E-04 8.61E-05 4 - 30 days 1.14E-07 3.79E-04 1.65E-04 IA6E-04 7.45E-05 ASSUMPTIONS: The methodology detailed in Regulatory Guide 1.194 is acceptable for determining atmospheric dispersion factor to the "control room".

DESIGN INPUT DOCUMENTS:

Calculation PNPS-1-ERHS-II.B-3, Rev. 0 Pilgrim Station Unit 1 Appendix I Evaluation AFFECTED DOCUMENTS:

METHODOLOGY: The computer program ARCON96 was used to calculate the X/Q's using the methodology incorporated in the program.

CALCULATION SHEET Entergy CALC NO. PN`PS-l-ERHS-llB-4 Revision I

Sheet 4 of 43

SUBJECT:

Control Room and Technical Support Center Accident Y/O's Using ARCON96 TABLE OF CONTENTS Section Page RECORD OF REVISIONS...

2 CALCULATION

SUMMARY

PAGE-_................

3 TABLE OFCONTENT................................

4 LIST OF EFFECTIVE PAE..

1.

BACKGROUND..................

7

2.

PURPOSE....................--...-..

5.

INPUT AND DESIGN CRTRA--

5.1 Mtoooy 5.2 Main Stack Release P.oint..

5.3 Turbine Building Release Pont-5.4 Turbine Building Reactor Feed Pump Area Release Point..._-._..................

5.5 Reactor Building Vent Release Point-.............

5.6 Reactor Building Trucklock Release Point.....................................

5.7 Control Room Receptor Location..-..---...--.....

5.8 Technical Support Center Receptoroato............-............

7.

CALCULATION/ANALYSIS..................................-......1 7.1 Meteorological Input.........--......--

~

1 7.2 Receptor I p

t.

.~1 7.3 Source ln u

1 7.4 VA lues 9 Input.

.1 7.6 Computer Run

.utput.............

22 7.6.1 Main Stack To Control Ro6m.........................................................

23 7.6.2 Mfain Stack To Technical Support Center...........................

25 7.6.3 Turbine Building To Control Room...................................................

27 7.6.4 Turbine Building To Technical Support Center.........................................

29 7.6.5 Turbine Building Reactor Feed Pump Area To C~ontrol Rooin..............................

3) 7.6.6 Turbine Building Reactor Feed Pump Area To Technical Support Center....................

33

CALCULATION SHEET Entergy CALC NO. PNPS-1-ERHS-II.B14 Revision I

Sh

SUBJECT:

Control Room and Technical Support Center Accident '/O's Using ARCON96

.eet 5 of 43 TABLE OF CONTENTS (Continued)

Section Pame 7.6.7 Reactor Building Vent To Control Room..........................................................

35 7.6.8 Reactor Building Vent To Technical Support Center.....................................

...................... 37 7.6.9 Reactor Building Trucklock To Control Room....................

....................................... 39 7.6.10 Reactor Building Trnckdock To Technical Support Center................................................................41

8.

RESULTS

v.............. 43 Table 8-1 Control Room Atmospheric Dispersion Factors (

Q

's)

.43 Table 8-2 Technical Support Center Atmospheric Dispersion Factors (X/Q's)..............................43 - Calculation-Design Verification.......-.-...-..........................

CALCULATION SHEET Entergy CALC NO. PNPS-I-ERHS-II.B-4 Revision I

Sheet 6 of 43.

SUBJECT:

Control Room and Technical Sulport Center Accident yI/Q's Using ARCON96 LIST OF EFFECTIVE PAGES Calculation Number:

PNPS-1-ERHS-II.B-4 Revision Number:

1 Page Revision 1 through 43 Attachment I (Al-I - Al-6)

I I

CALCULATION SHEET Entergy CALC NO. PNPS-I-ERHS-II.B-4 Revision I

Sh

SUBJECT:

Control Room and Technical Suvoort Center Accident 7L0's Usine ARCON96 eet 7 of 43.

1.

BACKGROUND Habitability of the main control room and other locations in the plant following design basis events must be evaluated. Atmospheric dispersion factors (X/Q's) from radioactivity release points to receptor locations are needed for calculation of estimated radiological consequences following postulated accidents.

2.

PURPOSE To calculate the atmospheric dispersion coefficients to the Control Room and Technical Support Center for releases from the Main Stack, Turbine Building roof, Reactor Building vent, and Reactor Building truck lock using 5 years of PNPS meteorological data and the computer program ARCON96, "Atmospheric Relative Concentrations in Building Wakes".

CALCULATION SHEET Entergy CALC NO. PNPS-1-ERHS-I.B-4 Revision I

Sheet 8

SUBJECT:

Control Room and Technical Support Center Accident I/O's Using ARCON96

3.

METHOD OF SOLUTION

__of 43.

The X/Q's to the Control Room and to the Technical Support Center are determined following the guidance provided in Regulatory Guide 1.194 [1]. The qualified computer program ARCON96 [2]

is used with the PNPS meteorological data documented in calculation PNPS-1-ERHS-II.B-3 [3]. The methodology for calculating the xXQ's is embodied in the ARCON96 computer program.

4.

ASSUMPTIONS The methodology described in Regulatory Guide 1.194, "Atmospheric Relative Concentrations For Control Room Radiological Habitability Assessments at Nuclear Power Plants," [1] is acceptable for determining atmospheric dispersion factors to the Control Room or similar locations.

CALCULATION SHEET Entergy CALC NO. PNPS-1-ERHS-II.B-4 Revision I

Sh

SUBJECT:

Control Room and Technical Supmort Center Accident vI0's Using ARCON96 eet 9 of 43.

5.

INPUT AND DESIGN CRITERIA The calculations of the X/Q's are based on the following data. The specific computer program parameter input values for each release point and receptor location are listed in the following sections.

5.1 Meteorology

1.

The meteorological data for the calendar years 1996, 1997, 1998, 1999, and 2000 are given in calculation PNPS-1-ERHS-HI.B-3 [3]. The computer input files identified for use with AR.CON96 are used. The files are as follows:

Elevated Release Ground-level Release (MS)

(TB, RB)

AR96A.met AR96B.met AR97A.met AR97B.met AR98A.met AR98B.met AR99A.met AR99B.met AROOA.met AROOB.met

2.

Wind speed measurement units = "mph" [3]

3.

Height of lower wind speed measurement on 160-ft meteorological tower = 33 ft [3] [4, Section B, page B-1] = 10 m

4.

Height of upper wind speed measurement on 160-ft tower = 160 ft [3] [4, Section B, page B-i] = 48.8 m

5.

Height of lower wind speed measurement on 220-ft meteorological tower = 33 ft [3] [4, Section B, page B-2] = 10 m

6.

Height of upper wind speed measurement on 220-ft tower = 220 ft [3] [4, Section B, page B-1] = 67.1 m

CALCULATION SHEET Entergy CALC NO. PNPS-1.ERHS-LB -4 Revision I

Sheet 10 of 43

SUBJECT:

Control Room and Technical Support Center Accident x/0's Using ARCON96

5.

INPUT AND DESIGN CRITERIA (Continued) 5.2 Main Stack Release Point

1.

Grade elevation of Main Stack (MS) = 65 ft [5]

2.

Height of Main Stack above grade elevation = 335 ft [4, App. B, page B-15] = 102.1 m

3.

Height of adjacent solid structures = 15 ft [5]. The height of the MS is more than twice the height of adjacent solid structures. Therefore, releases from the MS are considered elevated releases [1].

4.

Minimum MS accident flow rate from the Startiny 0+/-s5 Tieatment System (SGTS) = (4000

- 10%) cfm [6; 7] = 1.70 m3is. Flow rate from the SGTS is used since in the event of an accident, the safety-related SGTS will be available.

5.

Diameter of MS = 28.75 in (4, App. B, page B-15]. Radius 0.365 m.

5.3 Turbine Building Release Point

1.

Grade elevation at Turbine Building (TB) =23 ft [8F]

2.

Elevation of top of TB _ 108 ft [8F].

3.

Release height from the TB roof = (108 ft - 23 ft) = 85 ft = 25.9 m Releases from the TB roof are less than twice the height of adjacent solid structures (the TB). Consequently, releases from the TB during accident conditions are considered to be ground-level releases [1].

4.

Release from the TB roof exhausters is assumed to occur from the roof exhausters closest to the receptor locations.

5.

Vertical dimensions, above grade. of TB = 268 ft x 85 ft [SA, 8F].

The vertical cross-sectional area of the TB = (268 x 85) ft2 = 2116 m2.

CALCULATION SHEET Entergy CALC NO. PNPS-l-ERHS-II.B-4 Revision 1

Sheet 11 of 43.

SUBJECT:

Control Room and Technical Support Center Accident XIO's Using ARCON96

5.

INPUT AND DESIGN CRITERIA (CONTINUED) 5.4 Turbine Building Reactor Feed Pump Area Release Point

1.

Grade elevation at Turbine Building (TB) = 23 ft [8F1]

2.

Elevation of top of TB Reactor Feed Pump (RFP) area roof = 82 ft [81F].

3.

Release height from the TB RFP area roof = (82 ft - 23 ft) = 59 ft = 18 m Releases from the RFP area roof are less than twice the height of adjacent solid structures (the TB). Consequently, releases from this point during accident conditions are considered to be ground-level releases [1].

4.

Release from the TB RFP area roof exhausters is funneled to one release location.

5.

Vertical dimensions, above grade, of the RFP area and adjacent building = 59 ft x 74 ft [8A, 8F]. The vertical cross-sectional area = (59 x 74) ft2 = 406 i 2.

5.5 Reactor Building Vent Release Point

1.

Grade elevation of Reactor Building (RB) = 23 ft [8E]

2.

Elevation of top of RB vent = 182 ft [8D].

3.

Release height from RB vent = (182 ft - 23 ft) = 159 ft = 48.5 m

4.

Height of RB = 166 ft-23 ft = 143 ft [8E].

Releases from the RB vent are at a height less than twice the height of adjacent solid structures (the RB). Consequently, releases from the RB during accident conditions are considered to be ground-level releases [1].

5.

Vertical dimensions of RB (vent side), above grade = 142 ft x 143 ft [8E, 8C].

6.

The vertical cross-sectional area of the RB = (142 x 143) ft2 = 1886 M2

CALCULATION SHEET Entergy CALC NO. PNPS-I-ERHS-II.B4 Revision I

Sheet 12 of 43 SUBJECTr: Control Room and Technical Support Center Accident WIO's Using ARCON96

5.

INPUT AND DESIGN CRITERIA (CONTINUED) 5.6 Reactor Building Trucklock Release Point

1.

Grade elevation of Reactor Building (RB) = 23 ft [8E].

2.

Elevation of top of RB trucklock openincL = 43 ft [8D].

3.

Release height from RB trUcklock = (43 ft - 23 ft) = 20 ft 6.1 m Releases are conservatively assumed to be from top of opening.

4.

Height of RB =143 ft [§5.5.4].

Releases from the RB trucklock are at a height less than twice the height of adjacent solid structures (the RB). Consequently, releases from the RB trucklock during accident conditions are considered to be ground-level releases [1].

5.

Vertical dimensions of RB (trucklock side), above grade = 104 ft x 143 ft [8E, 8C].

6.

The vertical cross-sectional area of the RB = (104 x 143) ft2 = 1382 m2 5.7 Control Room Receptor Location The control room (CR) receptor location is the location of the CR air intake.

1.

Grade elevation of CR = 23 ft [8D]

2.

Elevation of CR intake 73 ft [8B, 8G]

3.

Distance of CR air intake from MS _ 800 ft [9] - 244 m

4.

Distance of CR air intake from main TB exhausters 138 ft [10]

42.1 m Distance measured perpendicular from the'two TB roof exhausters closest to CR intake.

5.

Distance of CR air intake from TB RFP area release point - 186 ft [10] _ 56.7 m

6.

Distance of CR air intake from RB vent = 160 ft [10] E 48.8 m

7.

Distance of CR air intake from RB trucklock _ 248 ft [8B, 101 _ 75.6 m S.

Direction from CR intake to MS 303 degrees [9]

9.

Direction from CR intake to TB 2 207 degrees [9, 10]

CALCULATION SHEET Entergy CALC NO. PNPS-I-ERHS-1I.B-4 Revision I-Sheet 13 of 43

SUBJECT:

Control Room and Technical Support Center Accident

_/O's Using ARCON96

5.

INPUT AND DESIGN CRITERIA (CONTINUED) 5.7 Control Room Receptor Location (Continued)

10.

Direction from CR intake to RFP area - 273 degrees [9, 10]

11.

Direction from CR intake to RB vent _ 285 degrees [9,10]

12.

Direction from CR intake to RB trucklock - 315 degrees [9]

5.8 Technical Support Center Receptor Location The Technical Support Center (TSC) receptor location is the location of the TSC air intake.

1.

Grade elevation of TSC = 23 ft [9]

2.

Height of TSC intake 10 ft above grade [11]

3.

Distance of TSC air intake from MS 920 ft [9]

280 m

4.

Distance of TSC air intake from TB 190 ft [9]

57.9 m

5.

Distance of TSC air intake from TB RFP area _ 300 ft [9]

91.4 m

6.

Distance of TSC air intake from RB vent - 280 ft [9] _ 85.3 m

7.

Distance of TSC air intake from RB trucklock _ 390 ft [9] _ 119 m

8.

Direction from TSC intake to MS 304 degrees [9]

9.

Direction from TSC intake to TB 256 degrees [9]

10.

Direction from TSC intake to TB RFP Area exhaust _ 285 degrees [9]

11.

Direction from TSC intake to RB vent 290 degrees [9]

12.

Direction from TSC intake to RB trucklock = 310 degrees [9]

CALCULATION SHEET Entergy CALC NO. PNPS-I-ERHS-IT.B-4 Revision I

Sheet _4_of 43.

SUBJECT:

Control Room and Technical Support Center Accident Y/O's Using ARCON96

6.

REFERENCES

1.

Regulatory Guide 1.194, "Atmospheric Relative Concentrations For Control Room Radiological Habitability Assessments at Nuclear Power Plants," June 2003.

2.

S&SACP34, Computer Program AICON96, Software Catalog No. 01811.

3.

Calculation PNPS-1-ERHS-II.B-3, "PNPS Meteorological Data For Calculation of Accident Atmospheric Dispersion Factors," Revision 0.

4.

Pilgrim Station Unit 1 Appendix I Evaluation, April 1977.

5.

Drawing M28, Equipment Location Main Stack & Filter Building.

"D.wnng M289. Reactor Building Air Plow ALdiagranr1.

7.

Technical Specification 3.7.B, Standby Gas Treatment System.

8.

Drawings A.

M14, Equipment Location Turbine Building Plan El. 151'-0" B.

Ml8, Equipment Location Reactor Building Plan El. 5'1'-0" C.

M19, Equipment Location Reactor Building Plan El. 74'-3" & El. 91'-3" D.

M22, Equipment Location Reactor Building Section C - C E.

M23, Equipment Location Section D-D & L-L.

F.

M24, Equipment Location Sections: E-E and F-F.

G.

M26, Equipment Locations Sections H-H, J-J, & K-K.

9.

Drawing C2, Site Plan.

10.

Drawing A6, Turbine and Reactor Building Roof Plan.

11.

Drawing M646, Technical Support Center Mechanical Floor Plan.

CALCULATION SHEET Entergy CALC NO. PNPS-I-ERHS-II.B4 Revision I

Sheet 15 of 43.

SUBJECT:

Control Room and Technical Support Center Accident 7/0's Using ARCON96

7.

CALCULATION/ANALYSIS The input to the ARCON96 computer program for determining the accident X/Q values was derived from the input parameter values given in Section 5.

7.1 Meteorological Input

1.

Number of meteorological data files = 5 [§5.1 #1]

2.

Meteorological data file names [§5.1 #1]:

A. Elevated release: AR96A, AR97A, AR98A, AR99A, AROOA B. Ground level release: AR96B. AR97B. AR98B. AR199B. AROOB

3.

Lower measurement height = 10 m [§5.1 #3, #5]

4.

Upper measurement height:

A. 160-ft tower-48.8 m [§5.1 #4]

B. 220-ft tower - 67.1 m [§5.1 #6]

4

5.

Wind speed units = "mph" [§5.1 #2]

7.2 Receptor Input

1.

Distance to receptor A. From Main Stack to

i.

CR = 244 m [§5.7 #3]

ii. TSC = 280 m [§5.8 #3]

B. From Turbine Building to

i. CR = 42.1 m [§5.7 #4]

ii. TSC = 57.9 m [§5.8 #4]

C. From TB RFP area to

i. CR = 56.7 m [§5.7 #5]

ii. TSC = 91.4 m [§5.8 #5]

D. From Reactor Building vent to:

i. CR = 48.8 m [§5.7 #6]

ii. TSC = 85.3 m [§5.8 #6]

CALCULATION SHEET Entergy CALC NO. PNPS-I-ERHS-.I.B-4 Revision I

Sheet 16 of 43

SUBJECT:

Control Room and Technical Support Center Accident X/O's Using ARCON96

7.

CALCULATION/ANALYSIS (CONTINUED) 7.2 Receptor Input (Continued)

E. From Reactor Building trucklock to:

i.

CR = 75.6 m [§5.7 #7]

ii. TSC = 119 m [§5.8 #7]

2.

Intake height A. CR [§5.7 #1, #2] = (73 ft - 23 ft) = 50 ft= 15.2 m B. TSC [§5.8 #2] = 10 ft = 3.05 m

3.

Elevation Difference = difference in grade elevation between release point and receptor location:

A. Main Stack to CR and TSC [§5.2 #1, 5.7 #1, 5.8 #1] = (65 ft - 23 ft) = 42 ft = 12.8 m B. Turbine Building and CR and TSC [§5.3 #1, 5.7 #1, 5.8 #1] = 0 m C. TB RFP Area and CR and TSC [§5.4 #1, 5.7 #1, 5.8 #1] = 0 m D. Reactor Building vent and CR and TSC [§5.5 #1,5.7 #1,5.8 #1] = 0 m E. Reactor Building trucklock and CR and TSC [§5.6 #1, 5.7 #1, 5.8 #1] =O m

4.

Direction to source A. From CR to

i. Main Stack = 303 degrees [§5.7 #8]

ii. Turbine Building = 207 degrees [§5.7 #9]

iii. TB RFP area = 273 degrees [§5.7 #10]

iv. Reactor Building vent = 285 degrees [§5.7 #11]

v. Reactor Building trucklock = 315 degrees [§5.7 #12]

B. From TSC to

i. Main Stack = 304 degrees [§5.8 #8]

ii. Turbine Building = 256 degrees [§5.8, #9]

iii. TB RFP area = 285 degrees [§5.8, #10]

iv.. Reactor Building vent = 290 degrees [§5.8 #11]

v. Reactor Building trucklock = 310 degrees [§5.8 #12]

CALCULATION SHEET Entergy CALCNO. PNPS-I-ERHS-IT.B-4 Revision I

Sheet 17 of 43

SUBJECT:

Control Room and Technical Support Center Accident T/Q's Using ARCON96

7.

CALCULATION/ANALYSIS (CONTINUED) 7.3 Source Input

1.

Release type:

A. From Main Stack = elevated [§5.2 #3]

B. From Turbine Building = ground [§5.3 #3]

C. From TB RFP are = ground [§5.4 #3]

D. From Reactor Building vent = ground [§5.5 #4]

E. From Reactor Building trucklock = ground [§5.6 #4]

2.

Release height (above grade):

A. From Main Stack = 102.1 m [§5.2 #2]

B. From Turbine Building = 25.9 m [§5.3 #3]

C. From TB RFP area = 18 m [§5.4 #3]

D. From Reactor Building vent = 48.5 m [§5.5 #3]

E. From Reactor Building trucklock = 6.1 m [§5.6 #3]

3.

Building area:

A.

For Main Stack = 0.01 [1] (not applicable for elevated release)

B.

For Turbine Building = 2116 m2 [§5.3 #5]

C.

For TB RFP area release = 406 m2 [§5.4 #5]

D.

For Reactor Building vent release = 1886 m2 [§5.5 #6]

E.

For Reactor Building trucklock release = 1382 m2 [§5.6 #6]

4.

Vertical velocity A.

For Main Stack vertical velocity (v) = 4.06 m/s [§5.2 #4, #5]

v = stack flow/stack cross-sectional area v = (1.70 m3/s)/(nrr2) = (1.70 m3/s)/{7t(0.365 M) 2 )

v =4.06 in/s B.

For Turbine Building =0 C.

For TB RFP area = 0

CALCULATION SHEET Entergy CALC NO. PNPS-I-ERHS-II.B-4 Revision I

Sheet 18 of 43.

SUBJECT:

Control Room and Technical Support Center Accident X/0's Using ARCON96

7.

CALCULATION/ANALYSIS (CONTINUED) 7.3 Source Input (Continued)

D.

For Reactor Building vent = 0 E.

For Reactor Building trucklock = 0 Stack flow (for Main Stack) = 1.70 m3/s [§5.2 #4]

,Stack radius (for Main Stack) = 0.365 m [§5.2 #5]

5.

6.

7.4 Values Input

1.

Surface roughness lengtn = U.20 [1]

2.

Wind direction window = 90 degrees [1]

3.

Minimum wind speed = 0.5 m/s [1]

4.

Averaging sector width constant = 4.3 [1]

5.

Initial diffusion coefficients (m) = 0 [1]

CALCULATIONSHEET Entergy CALC NO. PNl'S-I-IERhI S-iI.B-4 Revision I

Sheet 19 of 43.

SUBJECT:

Control Room and Technical Support Center Accident 7/0's Using ARCON96_

7.

CALCULATION/ANALYSIS (CONTINUED) 7.5 ARCON96 Input Main Stack Turbine Building Turbine Building!

Reactor Building!

Reactor Building Exhausters RFP Area Vent Trucklock.

CR TSC CR TSC CR TSC CR TSC CR TSC Meteorological Input Number of Met Data Files 5

5 5

5 Met Data File name Sec 7 1 #2A Sec 7.1 #I2B Lower Measurement Height (m) 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 Upper Measurement Height (m) 67.1 67.1 48.8 48.8 48.8 48.8 48.8 48.8 48.8 48.8 Wind Speed Units (mph, mi/s, knots) mph mph mph mph mph mph mph mplh mpnh mph Receptor Input Distance to Receptor (m) 244 280 42.1 57.9 56.7 91.4 48.8 85.3 75.6 119 Intake Height (in) 15.2 3.05 15.2 3.05 15.2 3.05 15.2 3.05 15.2 3.05 Elevation Difference (im) 12.8.

12.8 0

0 0

0 Direction to Sourcc (degrees) 303 304 207 256 273 285 285 290 315 310

CALCULATION SHEET Entergy CALC NO. PNPS-1I-ERHS-11.13-4 Revision I

Shi

SUBJECT:

Control Roomn and Technical Support Center Accident y/O's Using ARCON96 icet 20 of 43.

7.

CALCULATION/ANALYSIS (CONTINUED) 7.5 ARCON96 Input (Continucd)

Main Stack Turbine Buildina Turbine Bnilding Reactor Bluilding Reactor Building Exhiausters RFP Area Vent Trucklock CR TSC CR TSC CR TSC CR

'rsc CR TSC Source Input Release Type Stack Stack Ground Ground Ground Ground Ground Ground Ground Ground Release Hleight (m) 102.1 102.1 25.9 25.9 18.0 18.0 48.5 48.5 6.1 6.1 Building Area (m )

0.01 0.01 2116 2116 406 406 1886 1886 1382 1382 Vertical Velocity (m/s) 4.06 4.06 0

0 0

0 Stack Flow (m3Is) 1.70 1.70 0

0 0

0 Stack Radius (in) 0.365 0.365 0

0 0

0 Output Files Output File (namne) (*.log) mscrl mstsc I tbcrl tbtsc l rfpcI rrptsc I rbcrl rbtsc I rbticrl rbtltsc1 CFD File Name (*.cfd rnscrl mstscl tbcrl tbtsc I rrpcrl rfptscl rbcrl rbhsc I rbticrl rbtltsc I Expanded Output (y or n) n ii i

f

CALCUILATION SIIE!ET Entergy CALC NO. PNPS--Ir-RIIS-.I.B4 Revision I

Sheet 21 or 43.

SUBJECI:CT Control Room and Technical Support Center Accident XIO's Using ARCON96

7.

CA LCULATION/ANALYSIS (CONTINUED) 7.5 ARCON96 Input (Continuedl)

Main Stack Turbine Buildina Tuirbine Buildin Reactor Bnilding Reactor Building Exhntosters RFP Area Vent Trucklock CR TSC CR TSC CR TSC CR TSC CR TSC Values Surface roughness length (m) 0.20 0.20 0.20 0.20 0.20 0.20 0.20 0.20 0.20 0.20 Wind Direction Window (degrees) 90 90 90 90 90 90 90 90 90 90 Minimum Wind Speed (m/s) 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 Averaging Sector Width Constant 4.3 4.3 4.3 4.3 4.3 4.3 4.3 4.3 4.3 4.3 Initial Diffusion Coefficients (m) 0.0,0.0 0.0,0.0 0.0, 0.0 0.0,0.0 0.0, 0.0 0.0,0.0 0.0, 0.0 0.0,0.0 0.0, 0.0 0.0, 0.0 Hours in Averages 1, 2, 4, 8, 12 24, 96, 168, 360, 720 Minimum Number of Hours 1, 2, 4, 8, 11, 22, 87, 152, 324, 648

CALCULATION SHEET Entergy CALCNO. PNPS-I-ERHS-II.B-4 Revision I_

Sheet 2of 43

SUBJECT:

Control Room and Technical Support Center Accident X/O's Using ARCON96.

7.6 Computer Run Output The above information is input to the ARCON96 computer program. The computer run output is provided as follows:

Main Stack to Control Room

§7.6.1 Main Stack to Technical Support Center

§7.6.2 Turbine Building to Control Room

§7.6.3 Turbine Building to Technical Support Center

§7.6.4 TB RPB Area to Control Room

§7.6.5 TB RFP Area Technical Support Center

§7.6.6 Reactor Building Vent to Control Room

§7.6.7 Reactor Building Vent to Technical Support Center

§7.6.8 Reactor Building Trucklock to Control Room

§7.6.9 Reactor BuxIdir'g Trucklock to TechTiicPI $u.;'?ort Center

§7.6.10

CALCULATION SHEET Entergy CALC NO. PNPS-l-ERHS-TI.B-4 Revision I

SUBJECT:

Control Room and Technical Support Center Accident Y/Q's Using ARCON96 Sheet 23 of 43.

7.6 Computer Run Output (Continued) 7.6.1 Main Stack To Control Room Program

Title:

1ACoN96.

Developed For:

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date:

June 25, 1997 11:00 a.m.

NRC Contacts:

J. Y. Lee J.

J.

Hayes L.

A Brown Phone: (301) 415 1080 e-mail: jyllfnrc.gov Phone: (301),415 3167 e-mails jjhLnrc.gov Phone: (301) 415 1232 e-mail: lab2@nrc. gov Code Developer: J.

V. Ram dell Phone: (509) 372 6316 e-mail: JLramsdell@pnl gov Code Documentation:

NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 3/23/2004 at 09:57:18

- - - - ARCON INPUT **********

Number of Meteorological Data Files 5

Meteorological Data File Names C: \\.RCON96\\METDATA\\AR-A\\AR96A.MET C: \\ARCON96\\METDATA\\AR-A\\AR97A.2lT C: \\ARCON96\\ZTDATAXAR-A\\AR98A.MTU C: \\ JCON96\\MNETIATA\\AR-A\\AR99A.M)T C: \\.RCON96\\ML)TfATA\\AR-AARR00AJ. MT Height of lower wind instrument (m) 10.0 Height of upper wind instrument (in) 67.1 Wind speeds entered as miles per hour Elevated release Release height {m) 102.1 Building Area (m12)

.0 Effluent vertical velocity (mis) 4.06 Vent or stack flow (m43/s).

1.70 Vent or stack radius (m)

W

.37 Direction..

intake to source (deg)

Wind direction sector width (deg)

Wind direction window (deg)

Distance to intake (m)

Intake height (m)

Terrain elevation difference Cm) 303 90 258 - 348 244.0 15.2 12.8

CALCULATION SHEET CALC NO. PNPS-l-ERJS-IS.B-4 Revision I

Entergy Sheet 24 of 43.

SUBJECT:

Control Room and Technical SuRport Center Accident x/0's Using ARCON96 7.6 Computer Run Output (Continued) 7.6.1 Main Stack To Control Room (Continued)

Output file names chiq\\mscrl.log chiq\\mscrl.cfd Mini-m Wind Speed (m/s)

Surface roughness length (m)

Sector averaging constant Initial value of sigma y Initial value of sigma z

.5

.20 4.3

.00

.00 Expanded output for code testing not selected Total number of hours of data processed

43848 Hours of missing data

=

1488 Hours direction in window

13121 Hours elevated plume w/ dir.

in window 6701 Hours of calm winds 16 Hours direction not in window or calm

29223 DISTRIBUTION

SUMMARY

DATA BY AVER. PER.

UPPR LIM.

LOW LIX.

ASoVz RANCE IN RANGE BELZOS RXNGE ZERO TOTAL X/Qs

% PON ZERO I

1.*001-05 1.00Z-09 0.

4105.

0.

38255.

42360.

9.69 2

1.00Z-05 1.001-09 0.

5107.

0.

37022.

42129.

12.12 AVERAGING 4

1.00Z-05 1.001-09 0.

6838.

0.

34859.

41697.

16.40 INTERVAL 1.00Z-05 1.001-09 0.

9897.

63.

30901.

40861.

24.38 12 1.00Z-05 1.O00-09 0.

13156.

386.

27932.

41474.

32.65 24 1.00Z-05 1.00Z-09 0.

19852.

983.

20240.

41075.

50.72 96 1.00Z-05

1. 00Z-09 0.

34508.

1186.

4375.

40069.

89.08 168 1.00Z-05 1.00-09 0.

36911.

511.

1490.

38912.

96.17 360 1.00Z-05 1.O0Z-09 0.

38033.

0.

115.

38148.

99.70 720 1.00Z-05 1.00Z-09 0.

38529.

0.

38529.

100.00 95th PERCzzTT1z x/Q VALUzS 7.322-07 7.11Z-07 6.50Z-07 5.533-07 4.19Z-07 95% X/Q for standard averaging intervals 2.51Z-07 1.42Z-07 1.19Z-07 1.05Z-07 9.65E-08 0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1 to 4 days 4 to 30 days 7.32Z-07 4.93Z-07 9.98Z-08 1.06z-07 8.95z-08 HOURLY VALUE RANGE MAX X/Q 9.73Z-06 5.67Z-06 MIN X/Q 2.14Z-42 8.38E-43 CENTERLINE SECTOR-AVERAGE NORMAL PROGRAM COMPLETION

CALCULATION SHEET Entergy CALC NO. PNPS-l-ERHS-IT.B-4 Revision I

SUBJECT:

Control Room and Technical Surmort Center Accident v/O's Using ARCON96 Sheet 25 of 43.

7.6 Computer Run Output (C6ntinued) 7.6.2 Main Stack To Technical Support Center Program

Title:

ARCON96.

Developed For:

U.S. Nuclear Regulatory Connission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date:

June 25, 1997 11:00 a.m.

NRC Contacts:

J.

Y. Lee J. J. Hayes L. A Brown Phone: (301) 415 1080 e-mails jyllEnrc.gov Phones (301) 415 3167 e-mail: jjhLenrc.gov Phone: (301) 415 1232 e-mail: lab2enrc.gov Code Developer-J.

V. Ramsdell Phone: (509) 372 6316 e-mail: jJ.ramsdellfpnl.gov Code Documentation:

NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 3/23/2004 at 09:51s26

^*^-^^^ ARCON INPUT **^**^*

Number of Meteorological Data Files 5

Meteorological Data File Names C: %ARCON96%XETDATA\\AR-A\\AR96A.MET C: \\ARCON96\\METDATA\\AR-A\\1R97A.MET C: \\ARCON96\\NKEDATA\\AR-AM\\A98A.MET C: \\ARCON96\\METDATJAAR-A\\AP99A.MET C:\\ARCON96\\METDATA\\AR-A\\ARO0A.MET Height of lower wind instrument {m) 10.0 Height of upper wind instrument (m) 67.1 Wind speeds entered as miles per hour Elevated release Release height (m) 102.1 Building Area (m^2)

.0 Effluent vertical velocity (m/s)

U 4.06 Vent or stack flow (m-3/s) 1.70 Vent or stack radius (m)

-37 Direction.. intake to source (deg)

Wind direction sector width (deg)

Wind direction window (deg)

Distance to intake Cm) intake height (m)

Terrain elevation difference (m) 304 90 259 - 349 280.0 3.0 12.8

CALCULATION SHEET Entergy CALC NO. PNPS-I-ERHS-II.B.4 Revision I

SUBJECT:

Control Room and Technical Sunnort Center Accident vIO's Using ARCON96 Sheet 26 of 43.

7.6 Computer Run Output (Continued) 7.6.2 Main Stack To Technical Support Center (Continued)

Output file names chiq\\mstscl.log chiq\\mstscl.cfd Min4imi Wind Speed (m/s)

Surface roughness length (m)

Sector averaging constant Initial value of sigma y initial value of sigma z a

a

.5

.20 4.3

.00

.00 Expanded output for code testing not selected Total number of hours of data processed -

43848 Hours of missing data 1488 Hours direction in window a

13056 Hours elevated plume w/ dir. in window 6653 Hours of calm winds 16 Hours direction not in window or calm a

29288 DISZTRBUTION SM01ARY DATA BY AVER. PER.

1 2

UPPER LsM.

1.00E-04 1.00Z-04 LONW LIM.

1.0oz-08 1.00Z-08 ABOVE RASGE

0.

1N RANGE 4005.

4746.

BZLOW RANGE 104.

364.

2ZRO 38251.

37019.

TOTAL /Qs 42360.

42129.

% WON ZERO 9.70 12.13 AVERAGING INTERVAL 4

8 1.00-04 1.OOZ-04 1.00E-08 1.0OZ-08

0.

6163.

9003.

666.

930.

34868.

30928.

41697.

40861.

16.38 24.31 12 1.0oz-04 1.001-08 0.

12362.

1109.

28003.

41474.

32.48 24

1. 001-04 1.00Z-08 0.

19498.

1182.

20395.

41075.

50.35 96 1.00E-04 1.00Z-08 0.

33240.

2259.

4570.

40069.

88.59 168 1.00Z-04 1.00E-08 0.

36008.

1411.

1493.

38912.

96.16 360 1.00Z-04 1.00Z-08 0.

37485.

548.

115.

38148.

99.70 720 1.00z-04 1.00Z-08 0.

38346.

183.

0.

38529.

100.00

95th PEROCNTILz X/Q VALUES 9.23Z-07 9.04E-07 8.27E-07 7.06Z-07 5.41Z-07 95% X/Q for standard averaging intervals 3.23Z-07 1.841-07 1.53Z-07 1.33Z-07 1.23Z-07 o to 2 to 8 to 1 to 4 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 8 hours 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 4 days 30 days 9.23E-07 6.34Z-07 1.31Z-07 1.37Z-07 1.14E-07 HOURLY VALUE RANGE mmX /Q MmN X/Q 1.26Z-05 5.489-43 7.36Z-06 2.12Z-43 CENTERLINE SECTOR-AVERAGE NORMAL PROGRAM COMPLETION

CALCULATION SHEET Entergy CALC NO. PNPS-1-ERHS-TI.B-4 Revision I

Sheet 27 of 43

SUBJECT:

Control Room and Technical Support Center Accident y/Q's Using ARCON96 7.6 Computer Run Output (Continued) 7.6.3 Turbine Building To Control Room Program

Title:

ARCON96.

Developed For:

u.S. Nuclear Regulatory commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date:

June 25, 1997 11:00 a.m.

NRC Contacts:

J. Y.

Lee Phone:

(301) 415 1080 e-mail: jyllpnrc.gov J. J. Hayes Phone: (301) 415 3167 e-mail: jjhznrc.gov L. A Brown Phone: (301) 415 1232 e-mail: lab2enrc.gov Code Developer: J.

V. Ramidell Phones (509) 372 6316 e-w.il: jramsdellepnl.gov Code Documentation:

NU1ZG/CR-633l Rev.

1 The program was prepared for an agency of the United States Govern:ment. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 3/23/2004 at 09:22slO ARCON INPUT ******--

Number of Meteorological Data Files 5

Meteorological Data File Names C:\\ARCON96\\METDATA\\AR-B\\AR96B.MET C:\\ARCON96\\METDATA\\AR-B\\AR97B.XHT C:\\ARCON96\\METDATA\\AR-B\\AR98B.HHT Cs\\ARCON96\\MzTD.TA\\AR-B\\AR99B.MT C:EAXCON96X TDATA\\AR-B\\AR 0B.IMT Height of lower wind instrument Cm) 10.0 Height of upper wind instrument (m) 48.8 Wind speeds entered as miles per hour Ground-level release Release height (m) 25.9 Building Area (mA2) 2116.0 Zffluent vertical velocity (m/s)

.00 Vent or stack flow (m'3/s)

=

.00 Vent or stack radius {m)

.00 Direction..

intake to source (deg) 207 Wind direction sector width (deg) 90 Wind direction window (deg) 162 -

252 Distance to intake (m) 42.1 Intake height

{m) 15.2 Terrain elevation difference (m)

.0

CALCULATION SHEET Entergy CALC NO. PNPS-1-ERHS-I1.B-4 Revision I

Sheet 8

of 43.

SUBJECT:

Control Room and Technical Support Center Accident x/0's Using ARCON96 7.6 Computer Run Output (Continued) 7.6.3 Turbine Building To Control Room (Continued) output file names chiq\\tbcrl.log chiqgtbcrl.cfd Finimum Wind Speed (mls)

.5 Surface roughness length (m)

.20 Sector averaging constant 4.3 Initial value of sigma y

.00 Initial value of sigma z

.00 Expanded output for code testing not selected Total number of hours of data processed -

43848 Hours of missing data 1468 Hours direction in window

16627 Hours elevated plume w/ dir. in window 0

Hours of calm winds 666 Hours direction not in window or calm 25087 DISTRIBDTION

SUMMARY

DATA BY AVZRAGISG INTERVAL 95% X/Q for standard averaging intervals 0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 3.44E-03 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2.79E-03 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1.05E-03 1 to 4 days 8.86E-04 4 to 30 days 7.82E-04 HOURLY VALUE RANGE MAX X/Q 4.17E-03 2.43E-03 SECTOR-AVERAGE NORMAL PROGRAM COMPLETION MIN X/Q 7.94E-05 4.63E-05

CALCULATION SHEET En tergy CALC NO. PNPS-I-ERHS-I.B-4 Revision I

SUBJECT:

Control Room and Technical Support Center Accident L1Q'SUsing ARCON96 Sheet 29 of 43.

7.6 Computer Run Output (Continued) 7.6.4 Turbine Building To Technical Support Center Program

Title:

ARCON96.

Developed For:

M.S. Nuclear Regulatory Comunission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date:

June 25, 1997 11:00 a.m.

NRC Contacts:

J.

Y. Lee '

J. J.

Hayes L. A Brown Phone: (301) 415 1080 e-mails jyll=nrc

gov Phone: (301) 4i5 3167 e-mail: jjhnxrc.gov Phone: (301) 415 1232 e-mail: lab2fnrc.gov Code Developer: J. V. Ramsdell Phone:

(509) 372 6316 e-mails j ramsdellfpnl.gov Code Documentation:

NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Governsent. Neither the Unif1M States Government nor any agency thereof, nor any of their employees, makes any warranty, empressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 3/23/2004 at 09:23:05

- - - - ARCON NPVWT *******

Number of Meteorological Data Files 5

Meteorological Data File Names C: XARCON96%HETMTDA\\AR-BAR96B.MHE C: \\ARCON96\\MZTDTA\\AR-B\\AR97B.MET C: \\ARCON96 \\MTDATA\\AR-B\\AR98B.1ET C: \\ARCON96\\MERTDATA\\AR-B\\AR99B.)ST C: \\ARCON96 \\MEUDATA\\AR-B\\AR700B.MET Height of lower wind instrument {m) a Height of upper wind instrument (m)

Wind speeds entered as miles per hour Ground-level release Release height (m)

Building Area (m,2)

Effluent vertical velocity (m/S)

Vent or stack flow (mA3/s)

Vent or stack radius Wm) 10.0 48.8

-25.9 2116.0

.00

.00 a

Direction.. intake to source (deg)

Wind direction sector width (deg)

Wind direction window (deg)

Distance to intake (m)

Intake height Cm)

Terrain elevation difference (m) 256 90 211 - 301 57.9 3.0

.0

CALCULATION SHEET CALC NO. PNPS-1-ERHS-TI.B-4 Revision I

Entergy Sheet 30 of 43 SUBJECr: Control Room and Technical Support Center Accident X/Q's Using ARCON96 7.6. Computer Run Output (Continued) 7.6.4 Turbine Building To Technical Control Center (Continued)

Output file names chiq\\tbtscl.log chiq\\tbtacl.cfd Minimum Wind Speed (m/s)

.5 Surface roughness length (m)

.20 Sector averaging constant 4.3 initial value of sigma y initial value of sigma z a

.00

.00 Expanded output for code testing not selected Total number of hours of data processed -

43848 Hours of missing data 1468 Hours direction in window 15396 Hours elevated plume w/ dir. in window V

Hours of calm winds 66 Hours direction not in window or calm 26318 DISTRIBUTION SfMMARY DATA BY AVERAGING INTERVAL AVER. PER.

1 2

4 8

UPPER LXX.

rThOZ-02 1.00Z-02 1.00Z-02 1.00Z-02 LOW LEN.

1.00Z-06 1.00Z-06 1.00Z-06 1.00Z-06 ABOVZ RANGE

0.

IN RANCZ 16062.

18516.

22002.

26602.

BELOW RANGE

0.

ZERO 26318.

23678.

19825.

14496.

TOTAL X/Qs 42380.

42194.

41827.

41098.

% NON 2ZRO 37.90 43.88 52.60 64.73 95th PURCTEL1 S/0 VALUES 1.71Z-03 1.69Z-03 1.64z-03 1.531-03 12 1.00-02 1.00Z-06 0.

30541.

0.

11171.

41712.

73.22 24

1. 00Z-02 1.001-06 0.

36304.

0.

5399.

41703.

87.05 96 1.00E-02

1. 00-06 0.

40531.

21.

267.

40819.

99.35 168 1.00Z-02 1.00Z-06 0.

39644.

0.

39644.

100.00 360 1.00E-02 1.00E-06 0.

39975.

0.

39975.

100.00 720

1. 00Z-02 1.00Z-06 0.

39150.

0.

39150.

100.00 1.21Z-03 e.42Z-04 5.49Z-04 4.98Z-04 4.36E-04 4.021-04 95% X/Q for standard averaging intervals 0

2 a

1 4

to to to to to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 8 hours 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 4 days 30 days 1.71Z-03 1.44E-03 5.09E-04 4.51E-04 3.79z-04 HOURLY VALUE RANGE MAX X/Q

2.08Z-03 1.21Z-03 CZTZLINZ

SECTOR-AVERAGE MmN X/Q 8.73K-05 5.09E-05 NORMAL PROGRAM COMPLETION

CALCULATION SHEET CALC NO. PNPS-1-ERHS-1I.B.4 Revision I

Entergy Sheet 31 of 43.

SUBJECT:

Control Room and Technical Support Center Accident Xi/0's Using ARCON96 7.6 Computer Run Output (Continued) 7.6.5 Turbine Building Reactor Feed Pump Area To Control Room Program

Title:

ARCON96.

Developed For:

Date:

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management June 25, 1997 11:00 a.m.

NRC Contacts:

J. Y. Lee J. J. Hayes L. A Brown Phone:

(301) 415 1080 e-mail: jyllCnrc.gov Phone: (301) 415 3167 e-mail: jjhenrc.gov Phones (301) 415 1232 e-mail: lab2@nrc.gov Code Developer: J. V. Ransdoll Phone: (509) 372 6316 e-mail: jramdellepnl.gcv Code Documentation:

NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 3/26/2004 at 11:00:32

^***- ARCON ZNPVT *---..**..

Number of Meteorological Data Files -

5 Meteorological Data File Names C:\\ARCON96\\METD&TA\\AR-B\\AR96B.MZT C: \\ARCON96\\MZTDATA\\AR-B\\AR97B.MET C: \\ARCON96XMETDATA\\AR-B\\AR98B.MZT C:\\ARCON96\\MZTDATA\\AR-B\\AR99B.XET Cs\\ARCON96\\MXTDATA\\AR-B\\AROO.XET Height of lower wind instrument (m)

10.0 Height of upper wind instrument (m)

48.8 Wind speeds entered as miles per hour Ground-level release Release height (m)

Building Area (m*2)

Effluent vertical velocity (mis)

Vent or stack flow (m-3/s)

Vent or stack radius (m)

Direction..

intake to source (deg)

Wind direction sector width (deg)

Wind direction window (deg)

Distance to intake {m)

Intake height (m)

Terrain elevation difference (m)

.18.0 406.0

.00

.00 273 90 228 -

318 56.7 15.2

.0

CALCULATION SHEET CALC NO. PNPS-I-ERHS-II.B-4 Revision I

Entergy Sheet 32 of 43.

SUBJECT:

Control Room and Technical Support Center Accident Y/O's Using ARCON96 7.6 Computer Run Output (Continued) 7.6.5 Turbine Building Reactor Feed Pump Area To Control Room (Continued)

Output file names chiq\\rfpcrl.log chiq\\rfpcrl.cfd Minimum Wind Speed (m/s)

Surface roughness length (m)

Sector averaging constant Initial value of sigma y Initial value of sigma z

.5

.20 4.3

.00

.00 Expanded output for code testing not selected Total Hours Hours Hours Hours Hours number of hours of data processed -

43848 of missing data 1468 direction in window

13719 elevated plums w/ dir. ir-window 0

of calm winds 6C6 direction not in window or calm

27995 DISTR3hUTION SUWDUURY DATrA BY AVERAGING AVER. PER.

UPPER LIX.

L4OW LXX.

ABOVE RANGE 1N RANCE I

IG B.ZCC RANGZ ZERO TOTAL X/Qs

% NON ZERO 1

1.00Z-02 1.00Z-06 0.

14385.

0.

27995.

42380.

33.94 2

1.00-02 1.00Z-06 0.

16538.

0.

25656.

42194.

39.20 4

1.00Z-02 1.00Z-06 0.

19647-0.

22180.

41827.

46.97 INTERVAL 1.00Z-02 1.001-06 0.

23938.

0.

17160.

41098.

5B.25 12 1.001-02 1.001-06 0.

27871.

0.

13841.

41712.

66.82 24 1.00Z-02 1.00Z-06 0.

34389.

0.

7314.

41703.

82.46 96 1.00Z-02 1.001-06 0.

40463.

0.

356.

40819.

99.13 168 1.00E-02 1.00Z-06 0.

39644.

0.

39644.

100.00 360 1.00Z-02 1.00Z-06 0.

39975.

0.

39975.

100.00 720 1.00Z-02 1.00Z-06 0.

39150.

0.

39150.

100.00 95kt PzRceNwL Zx/Q vAL=ES 2.042-03 2.01Z-03 1.95Z-03 1.79Z-03 1.44Z-03 9.93Z-04 6.351-04 5.79E-04 5.14E-04 4.87E-04 95% X/Q for standard averaging intervals 0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1 to 4 days 4 to 30 days 2.04Z-03 1.70Z-03 5.95Z-04 5.16Z-04 4.64Z-04 HOURLY VALUE RANGE

.MAX X/Q 2.54Z-03 1.48Z-03 CENTERLINE SECTOR-AVERAGE MIN X/Q 1.42Z-04 8.29Z-05 NORMAL, PROGRAM COMPLETION

CALCULATION SHEET Entergy CALC NO. PNPS-1-ERHS-11.B-4 Revision I

Sheet 33 of 43

SUBJECT:

Control Room and Technical Support Center Accident Y/0's Using ARCON96 7.6 Computer Run Output (Continued) 7.6.6 Turbine Building Reactor Feed Pump Area To Technical Support Center Program

Title:

ARCON96.

Developed For:

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date:

June 25, 1997 11:00 a.m.

NRC Contacts:

J. Y. Lee Phone: (301) 415 1080 e-mail: jyllEnrc.gov J. J. Hayes Phone: (301) 415 3167 e-mail: jjhenrc.gov L. A Brown Phone: (301) 415 1232 e-mail: lab20nrc.gov Code Developers J.

V. Pamsdell Phone: t509) 372 6316 e-mail. jramsdellepnl.gov Code Documentation:

InRZG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government.

Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of iny portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 3/26/2004 at 14:19s13 ARCON ZNPUT

Number of Meteorological Data Files 5

Meteorological Data File Names C: ARCON96\\EzTDATA\\AR-B\\AR96B.MET C:\\ARCON96\\METDATA\\AR-B\\AR97B.x=

C:\\ARCON96\\XMTDATA\\AR-B\\AR98B.MET C: \\ACON96\\MZTDATA\\AR-B\\AR99B.)ET C:\\ARCoN96\\MzTDATA\\AR-n\\AR00B.MET Height of lower wind instrument (m) 10.0 Height of upper wind instrument (m) -

48.8 Wind speeds entered as miles per hour Ground-level release Release height (m) 18.0 Building Area (m42) 406.0 Effluent vertical velocity (m/s) a

.00 Vent or stack flow (mi3/s)

.00 Vent or stack radius Cm)

.00 Direction.. intake to source (deg) 285 Wind direction sector width (deg) 90 Wind direction window (deg) 240 -

330 Distance to intake (m) 91.4 Intake height (m) 3.0 Terrain elevation difference (m)

.0

CALCULATION SHEET CALC NO. PNPS-1-ERHS-IT.B-4 Revision I

Entergy Sheet 34 of 43.

SUBJECT:

Control Room and Technical Support Center Accident y/O's Using ARCON96 7.6 7.6.6 Computer Run Output (Continued)

Turbine Building Reactor Feed Pump Area To Technical Support Center (Continued)

Output file names chiq\\rfptscl.log chiq\\rfptscl.cfd Minimum Wind Speed (m/s)

Surface roughness length (m)

Sector averaging constant

.5

.20 4.3 Initial value of sigma y Initial value of sigma z

.00

.00 Expanded output for code testing not selected Total number of hours of data processed -

43848 Hours of missing data 1468 Hours direction in window 12895 Hours elevated plume w/ dir. in window 0

Hours of calm winds 666 aouts direction not in window or calm 28819 DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL AVER.

PER.

UPPER Li.

LOw LEX.

ADOVE IAM 5N RJ%=E BELOW RAJZZ1 ZERO TOTAL X/Qs X MON ZERO 1

1.005-02 1.00E-06 0.

13561.

ti O0.

28819.

42380.

32.00 2

1.005-02 1.005-06 0.

15559.

0.

26635.

42194.

36.87 1.001-6 1.00Z-06 0.

18404.

0.

23423.

41827.

44.00 8

1.00z-02 1.00X-06 0.

22351.

0.

18747.

41098.

54.38 12 1.00Z-03 1.00z-07 0.

_ 26128.

0.

15584.

41712.

62.64 24 1.005-03 1.001-07 0.

32882.

O.

8821.

41703.

78.85 96 1.00E-03 1.00E-07 0.

40314.

0.

505.

40819.

98.76 168 1.00Z-03 1.00Z-07 0.

39644.

0.

39644.

100.00 360 1.00Z-03 1.00Z-07 0.

39975.

0.

39975.

100.00 720 1.005-03 1.001-07 0

O.

39150.

0.

39150.

100.00 95th PERcE=NLZ XIQ VALUES 7.99z-04 7.79E-04 7.43E-04 6.771-04 5.44Z-04 3.78E-04 2.321-04 2.06E-04 1.855-04 1.74z-04 95% X/Q for standard averaging intervals 0 to 2 to 8 to 1 to 4 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 8 hours 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 4 days 30 days 7.99E-04 6.37E-04 2.29E-04

1. 841-04 1.65E-04 HOURLY VALUE RANGE MAX X/Q 1.00E-03 5.86E-04 CENTPRLINE SECTOR-AVERAGE MIN X/Q 3.88E-05 2.26E-05 NORMAL PROGRAM COMPLETION

CALCULATION SHEET CALC NO. PNPS-I-ERHS-II.B-4 Revision I

Entergy Sheet 35 of 43 -

SUBJECT:

Control Room and Technical Support Center Accident y1O's Using ARCON96 7.6 Computer Run Output (Continued) 7.6.7 Reactor Building Vent To Control Room Program

Title:

ARCoN96.

Developed For:

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date:

June 25, 1997 11:00 a.m.

NRC Contacts:

J. Y. Lee J. J. Hayes L. A Brown Phone: (301) 415 1080 e-mail: jyllenrc.gov Phone: (301) 415 3167 e-mail: jjhznrc.gov Phone: (301) 415 1232 e-mail: lab2Qnrc.gov Code Developer: J. V. Ramadell Phone: (509) 372 631f e-mail: J;ramdellIpri. gov Code Documentation:

NOHZG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 3/23/2004 at 09:25:S7

-'**~*

ARCON INPUT Number of Meteorological Data Files Meteorological Data File NSames C s ARCON96 \\M)TATA\\AR-B\\XAR96f B.MET C: %ARCON96%M`TDATAAR-B\\AR97B.HzT C:\\ARCON96\\METDATA\\AR-B\\AR9B. MET C:\\ARCON96]M2T xTA\\AR-BAR99B.MZT C: \\ARCON96METDATA\\AR-B\\AR00B.MET 5

Height of lower wind instrument (m) w Height of upper wind instrument (m) -

Wind speeds entered as miles per hour Ground-level release Release height (m)

Building Area (m42)

Effluent vertical velocity (mxs)

Vent or stack flow (mC3/s)

Vent or stack radius (m) 10.0 48.8 48.5 1886.0

.00

.00 0

M a

Direction..

intake to source (deg)

Wind direction sector width (deg)

Wind direction window (deg)

Distance to intake (m)

Intake height (m)

Terrain elevation difference Cm)

M 285 90 240 - 330 48.8 15.2

.0

CALCULATION SHEET CALC NO. PNPS-1-ERHS-ll.B-4 Revision I

Entergy Sheet 36 of 43.

SUBJECT:

Control Room and Technical Support Center Accident v/O's Using ARCON96 7.6 7.6.7 Computer Run Output (Continued)

Reactor Building Vent To Control Room (Continued)

Output file names chiq~rbcrl.log chiq\\rbcrl.cfd Minimum Wind Speed (m/s)

Surface roughness length (m)

Sector averaging constant a

.5

.20 4.3 Initial value of sigma y Initial value of sigma z

.00

.00 Expanded output for code testing not selected Total Hours Hours Houzs Houvs Hours number of hours of data processed -

43848 of missing data 1468 direction in window

13429 elevated plume w/ dir. in window -

0 of calm winds 956 direction not in window or calm 27995 DISTRIBUTION SOMMARY DATA BY AVZRAGflO NZUERVAL AVER.

PER.

UPPER LIM.

LOW LIX.

asovz RANG IN XAiW3 BELOW RANGE ZERO TOTAL X/Qs

% NON ZERO 1

2 4

1.00Z-02 1.00Z-02 1.00Z-02 1.00-06 1.00Z-06 1.00Z-06

0.

14385.

16377.

19232.

0.

40.

0.

27995.

25817.

22595.

42380.

42194.

41827.

33.94 38.81 45.98 S

1.00Z-02 1.00z-06 0.

23136.

0.

17962.

41098.

56.29 12 1.0 0-02 1.003-06 0.

26836.

0.

14876.

41712.

64.34 24

1. 00Z-02 1.O00-06 0.

J3297.

0.

8406.

41703.

79.84 96 1. 00Z-02

1. 00Z-06 0.

40258.

2.

559.

40819.

98.63 168 1.00Z-02

1. 00-06 0.

39644.

0.

39644.

100.00 360

1. 00-02 1.00Z-06 39973.

0.

39975.

100.00 720 1.00Z-02 1.00Z-06 0.

39150.

0.

39150.

100.00 95th PZRCZN5XLE X/IQ VZULZS 1.85Z-03 1.80Z-03 1.69Z-03 1.55Z-03 1.24E-03 8.613-04 5.313-04 4.69Z-04 4.31Z-04 4.01Z-04 95% X/Q for standard averaging intervals 0 to 2 to 8 to 1 to 4 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months a hours 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 4 days 30 days 1.85Z-03 1.45E-03 5.19Z-04 4.21E-04 3.81E-04 HOURLY VALUE RANGE M=X X/Q 2.30E-03 1.34E-03 CENTERLINE SECTOR-AVERAGE MIX X/Q 6.35E-05 3.70Z-05 NORMAL PROGRAM COMPLETION

CALCULATION SHEET CALC NO. PNPS-I-ERHS-II.B-4 Revision I

Entergy Sheet 37 of 43 -

SUBJECT:

Control Room and Technical Support Center Accident Y/Q's Using ARCON96 7.6 Computer Run Output (Continued) 7.6.8 Reactor Building Vent To Technical Support Center Program

Title:

ARCON96.

Developed For:

U.S. Nuclear Regulatory Comriision office of Nuclear Reactor Regulation.

Division of Reactor Program Management Date; June 25, 1997 11:00 a.m.

NRC Contacts:

J. Y. Lee J. J. Rayes L. A Brown Phone: (301) 415 1080 e-mail: jyllfnrc.gov Phones (301) 415 3167 e-mail: jjhbnrc.gov Phone: (301) 415 1232 e-mail: lab2e@rc.gov Code Developer: Z. V. Ramsdell Phone: (509) 372 6316 e-mail: jramsdellepnl.gay Code Documentation:

NuREG/CR-6331 Rev. 2 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or izplied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this progrrm or represents that its use by such third party would not infringe privately-owned rights.

Program Run 3/26/2004 at 13s36s24 ARCON INPUT ***-****.O Number of Meteorological Data Files 5

Meteorological Data File Names Cs\\ARCON96\\

=TDATA\\AR-B\\AR96B.NZT C: \\ARCON96MTDATA\\AR-D\\AR97B.MXE C:\\ARCON96\\METD&TA\\AR-B\\AR98B.MZT C:\\ARCON96\\MZTDATA\\AR-B\\AR99B.MZT C:\\ARCON96MXHTDATA\\AR-B\\AROOB.MZT Height of lower wind instrument (m) w Height of upper wind instrument (m)

Wind speeds entered as miles per hour Ground-level release Release height (m)

Building Area (nA2)

Effluent vertical velocity (mig)

Vent or stack flow (WV3/s)

Vent or stack radius (m) ft 10.0 48.8 48.5 1886.0

.00

.00 Direction.. intake to source (dog)

Wind direction sector width (deg)

Wind direction window (deg)

Distance to intake {m)

Intake height (m)

Terrain elevation difference {m) 290 a

90 245 - 335 85.3 a

3.0 a

.0

CALCULATION SHEET CALC NO. PNPS-l-ERHS-I1.B-4 Revision I

Entergy Sheet 38 of 43.

SUBJECT:

Control Room and Technical Support Center Accident y/Q's Using ARCON96 7.6 Computer Run Output (Continued) 7.6.8 Reactor Building Vent To Technical Control Center (Continued)

Output file names chiq\\rbtscl.log chiq\\rbtscl.cfd Minimum Wind Speed (m/s)

Surface roughness length (m)

Sector averaging constant

.5

.20 4.3 initial value of sigma y initial value of sigma z

.00

.00 Expanded output for code testing not selected Total number of hours of data processed a 43848 Hours of missing data 1468 Hours direction in window

=

13224 Hours elevated plm=e w/ dir.

in window 0

Hours of calm winis 956 Hours direction not,n wiadow or calm 28200 DXSTR1BUTZON

SUMMARY

DA5A BY AVERAGING INTERVAL AVER.

PER.

UPPZR LlX.

LOW LIt.

ABOVE RADINZ IN RANS=

BELOW RANGE ZERO TOTAL X/Os

% NW ZER

-l 1.00Z-03 1.00z-07 0.

14180.

0.

28200.

42380.

33.46 2

1.00Z-03 1.001-07 0.

16133.

0.

26061.

42194.

38.24 A

1.00Z-03 1.00z-07 0.

18942.

01 22885.

41827.

45.29 8

1.00z-03

1. 00z-07 0.

22793.

0.

18305.

41098.

55.46 12 1.00E-03 1.00z-07 0.

26442.

0.

15270.

41712.

63.39 6 24 1.0

.-03 1.00z-07 0.

32919.

0.

8784.

41703.

78.94 96 1.00z-03 1.00z-07 0.

40244.

0.

575.

40819.

98.59 168 1.00z-03

1. 00z-07 0.

39644.

0.

39644.

100.00 360 1.00z-03

1. 00z-07 0.

39975.

0.

39975.

100.00 720 1.005-03 1.00z-07 0.

39150.

0.

39150.

100.00 95th PEzRazNLz X/Q VALUS 7.26z-04 7.02z-04 6.63z-04 6.03E-04 4.81Z-04 3.33Z-04 2.03E-04 1.79E-04 1.655-04 1.545-04 95% X/Q for standard averaging intervals 0 to 2 to 8 to 1 to 4 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 8 hours 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 4 days 30 days 7.26Z-04 5.61Z-04 1.98Z-04 1.60Z-04 1.46Z-04 HOURLY VALUE RANGE MAX X/Q 8.965-04 5.22E-04 CENTERLINE SECTOR-AVERAGE MIN X/Q 2.54Z-05 1.48Z-05 NORMAL PROGRAM COMPLETION

CALCULATION SHEET Entergy CALC NO. PNPS-1-ERHS-II.B-4 Revision I

SUBJECT:

Control Room and Technical Support Center Accident Sheet 39 of 43.

,Y10's Using ARCON96 7.6 Computer Run Output (Continued) 7.6.9 Reactor Building Trucklock To Control Room Program

Title:

ARCON96.

Developed For:

Date:

NRC Contacts:

U.S. Nuclear Regulatory commission Office of Nuclear Reactor Regulation Division of Reactor Program Management June 25, 1997 11:00 a.m.

J. Y. Lee J. J. Hayes L. A Brown Phone:

(301) 415 1080 e-mail: jyllfnrc.gov Phone: (301) 415 3167 e-mail: jjhenrc.gov Phones (301) 415 1232 e-mails lab2fnrc.go7 Code Developer: J. V. Ramsdell. Phones (509) 372 6316 e-mail: j ramzdellepnl.gov Code Documentation: 2MREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represe.tu that its use by such third party would not infringe privately owned rights.

Program Run 3/23/2004 at 09:28s27

- - - - ARCON NPVT *I**N**P*U Number of Meteorological Data Files Meteorological Data File Names C: ARCON96\\ D ATJ\\AR-B\\AR96B.XET C:\\ARCON96\\2ZMDATA\\AR-B\\AR97B.XZT C:\\A CN96\\MZTDA\\A\\AR-B\\AR98B.MET C:\\ARCON96\\METDATA\\AR-B\\AR99B.MzT C:\\ARCON96\\

TDATA\\AR-B\\AROOB.MET Height of lower wind instrument (m)

Height of upper wind instrument (m)

Wind speeds entered as miles per hour N

S Ground-level release Release height (m)

Building Area (mW2)

Effluent vertical velocity (m/s)

Vent or stack flow (mA3/s)

Vent or stack radius (m)

Direction..

intake to source (deg)

Wind direction sector width (dog)

Wind direction window (deg)

Distance to intake (m)

Intake height Cm)

Terrain elevation difference {m) 10.0 48.8 6.1 1382.0

.00

.00 315 90 270 - 360 75.6 15.2

.0

CALCULATION SHEET CALC NO. PNPS-1-ERHS-ll.B-4 Revision I

Entergy Sheet 40 of 43.

SUBJECT:

Control Room and Technical Sunnort Center Accident Y/Q's Using ARCON96 7.6 7.6.9 Computer Run Output (Continued)

Reactor Building Trucklock To Control Room (Continued)

Output file names chiq\\rbtlcrl.log chicZ\\rbtlcrl. cfd Miniimn Wind Speed (mis)

Surface roughness length (m)

Sector averaging constant

.5

.20 4.3 Initial value of sigma y Initial value of sigma z

.00

.00 Expanded output for code testing not selected Total Hours Hours Huuxrs Hours Hours number of hours of data processed -

of missing data direction in window elevated plume w/ dir. in nindow of calm winds direction not in window or calm 43848 1468 10322 0

666 31392 DIST RIBUTXON SUMKPRY DATA BY AVERAGING INTERVAL 95% XVQ for standard averaging intervals 0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1 to 4 days 4 to 30 days 9.37E-04 7.39E-04 2.71Z-04 1.86E-04 1.58E-04 HOURLY VALUE RANGE MAX X/Q

)IN X/Q 1.42Z-03 5.54z-05 8.27E-04 3.23E-05 CZNTzRLn;E SECTOR-AVERAGE NORMAL PROGRAM COMPLETION

CALCULATION SHEET Entergy CALC NO. PNPS-1-ERHS-ll.B-4 Revision I

SUBJECT:

Control Room and Technical SuPport Center Accident 7/O's Using ARCON96 Sheet 41 of 43.

7.6 Computer Run Output (Continued) 7.6.10 Reactor Building Trucklock To Technical Support Center Program

Title:

ARCON96.

Developed For:

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date:

June 25, 1997 11:00 a.m.

NRC Contacts:

J.

Y. Lee J.

J.

Hayes L. A Brown Phone: (301) 415 1080 e-mail: jyllLnrc.gov Phone: (301) 415 3167 e-mail: jjh hnrc.gov Phone: (301) 415 1232 e-mail: lab20nrc.gov Code Developer: J.

V. Ram dell Phone: (5n9i. 372 6316 e-mail: j_razdelllpnl.gov.

Code Documentation:

NURZG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its Rose by such third party would not infringe privately owned rights.

Program Run 3/23/2004 at 09:29:13 ARCON INPUT ********

Number of Meteorological Data Files a

5 Meteorological Data File Names Cs *ARCON96 \\ITDATAJ\\AR-B\\AR96B.YET C:\\A\\CON96\\METDATAR-B\\AR97B. MT C:\\ARCON96\\METDATA\\AR-B\\AR98B.NET C:\\ARCON96\\METDATA\\AR-B\\AR99B.MET C:\\MACON96\\METDATA\\R-B\\AR00B.ME?

Height of lower wind instrument (m) 10.0 Height of upper wind instrument (m) 48.8 Wind speeds entered as miles per hour Ground-level release Release height {m) a 6.1 Building Area (mA2) 1382.0 Effluent vertical velocity (m/s)

.00 Vent or stack flow (m-3/s)

.00 Vent or stack radius (m)

.00 Direction..

intake to source (deg)

Wind direction sector width (deg)

Wind direction window (deg)

Distance to intake (m)

Intake height (m)

Terrain elevation difference (m) 310 90 265 -

355 119.0 3.0

.0

CALCULATION SHEET CALC NO. PNPS-1-ERHS-II.B-4 Revision I

Entergy Sheet 42 of 43.

SUBJECT:

Control Room and Technical Support Center Accident Yx/'s Using ARCON96 7.6 Computer Run Output (Continued) 7.6.10 Reactor Building Trucklock To Technical Support Center (Continued)

Output file names chiq~rbtltscl.log chiq\\rbtltscl.cfd Minimum Wind Speed (m/s)

Surface roughness length (m)

Sector averaging constant Initial value of sigma y Initial value of siga 2

.5

.20 4.3

.00

.00 expanded output for code testing not selected Total Hours Hours Hours Hours Hours number of hours of data processed -

43848 of missing data 1468 direction in window a

11066 elevated plume w/ dir. in window 0

of calm winds 666 direction not in window or calm 30648 DISTRIBUTION SUMM(ARY DATA BY XVERAGING AVER.

PER.

UPPER LIM.

LOW LIX.

ABOVE RASCE IN RANGE BELOW RANGE ZERO TOTAL X/IQ

% NOR ZERO 1

1.00E-03 1.00E-07 0.

11732.

0.

30648.

42380.

27.68 2

1.00E-03 1.00E-07 0.

13535.

0.

28659.

42194.

32.08 4

1.00Z-03 1.00Z-07 0.

16259.

0.

25568.

41827.

38.87 8

1.00Z-03 1.001-07 0.

20185.

0.

20913.

41098.

49.11 12 24 1.00Z-03 1.00Z-03 1.00Z-07 1.00Z-07

0.

23962.

30976.

0.

(,

17750.

10727.

41712.

41703.

57.45 74.28 96 1.001-03

1. 00z-07 0.

40223.

0.

596.

40819.

98.54 168 1.00Z-03

1. 00z-07 0.

39635.

0.

9.

39644.

99.98 360 1.00E-03

1. 00z-07 0.

39975.

0.

39975.

100.00 720 1.00Z-03 1.00Z-07 0.

39150.

0.

39150.

100.00 95th PERCENTILE XO VALUES 4.34Z-04 4.271-04 4.04E-04 3.59Z-04 2.90Z-04 2.03Z-04 1.15E-04 1.03Z-04 8.93Z-05 7.99Z-05 95% X/Q for standard averaging intervals 0 to 2 to 8 to 1 to 4 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 8 hours 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 4 days 30 days 4.34E-04 3.34E-04 1.24E-04 8.61E-05 7.45E-05 HOURLY VALUE RANGE MAX X/Q MIN X/Q 6.08E-04 2.46E-05 3.54E-04 1.44E-05 SECTOR-AVERAGE NORMAL PROGRAM COMPLETION

CALCULATION SHEET Entergy CALC NO. PNPS-I-ERHS-II.B-4 Revision I

Sh

SUBJECT:

Control Room and Technical Sun~ort Center Accident Y/O's Usinc ARCON96 eet 43 of 43.

8.

RESULTS The results of the ARCON96 computer runs are provided below.

Table 8-1 Control Room Atmospheric Dispersion Factors (X/Q's)

X/Q.(s/m3) to Control Room From 1

Time Interval Main Stack TB TB RFP Area RB Vent 0 - 2 hrs 7.32E-07 3.44E-03 2.04E-03 1.85E-03 2 - 8 hrs 4.93E-07 2.79E-03 1.70E-03 1.45E-03

- 2A hours 9.98E-08 1.05E-03 5.95E-04 5.19E-04 1 -4 days 1.06E-07 8.86E-04 5.16E-04 4.21E-04 4 - 30 days 8.95E-08 7.82E-04 4.64E-04 3.8 iE-04 Table 8-2 Technical Support Center Atmospheric Dispersion Factors (X/Q's)

X/Q (s/m3) to Tecnnical Support Center From Time Interval Main Stack TB TB RFP Area RB Vent RB Trucklock 0 - 2 hrs 9.23E-07 1.71E-03 7.99E-04 7.26E-04 4.34E-04 2 - 8 hrs 6.34E-07 1.44E-03 6.37E-04 5.6 1E-04 3.34E-04 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1.3 IE-07 5.09E-04 2.29E-04 1.98E-04 1.24E-04 1 -4 days 1.37E-07 4.51E-04 1.84E-04 1.60E-04 8.61E-05 4 - 30 days 1.14E-07 3.79E-04 1.65E-04 1.46E-04 7.45E-05

Calc No. _PNPS-1-ERHS-II.B-4 Entergy Revision 1

Sheet Al-1 of Al-6.

I Subiect: Control Room and Technical Support Center Accident v/Q's Using ARCON96 - Calculation Design Verification ATTACHMENT 9.1 DESIGN VERIFICATION COVER PAGE DESIGN VERIFICATION COVER PAGE 0 IP-2 0 IP-3 0 JAF IEI PNPS 0 VY Document No. ERHS-II.B-4 Revision Page 1 of &o 1

Title:

Control Room and Technical Support Center Accident y/Q's Using ARCON96 Ed Quality Related 0 Non Quality Related DV Method:

0 Design Review 0 Alternate Calculation 0 Qualification Testing VERIFICATION DISCIPLINE VERIFICATION COMPLETE AND COMMENTS REQUIRED RESOLVED (DViprint, sign, and date)

Electrical Mechanical Instrument and Control Civil/Structural Nuclear Systems and Safety

'--7 Print/Sign After Comments Have Been Resolved Originator:

pfA1 /ZL /t 7r K<W47&954 Date:

62 22,

_/S 61

//

R -Qvry

3/.3

//

0 A-Calculation Design Verification Checklist Page / of

Calc No.

PNPS-1-ERHS-II.B-4 Entergy Revision 1

Sheet A1-2 of A1-6.

Subiect: Control Room and Technical SUDOort Center Accident y/Q's Usina ARCON96 - Calculation Design Verification ATrACHMENT 9.7 CALCULATION DESIGN VERIFICATION CHECKLIST gPae 1 of 5 IDENTIFICATION:

DISCIPLINE:

DocumentTitle:

Control Room and Technical Support Center Accident x/Q's E CiviVStructural Using ARCON96 El Electrical Doc. No.:

PNPS-1-ERHS-II.B-4 Rev. 1 QA Cat. 0 EI&C D-,

K19R)97_AS 5

//

y El Mechanical Verifier:

Print SinDate Manager authorization El Nuclear for supervisor 3 Other-S&SA performing Ohr-SS verification.

0 N/A Print Sign Date METHOD OF VERIFICATION:

Design Review X Alternate Calculations a Qualification Test E 1

Design Inputs - Were the inputs correctly selected and Reference incorporated into the design?

Page No. _

Design Inputs include design bases, plant operational conditions, performance OR requirements, regulatory requirements and commitments, codes, standardsP field data, etc. An information used as design Inputs should have been Paragraph No.

reviewed and approved by the responsible design organization, as applicable.

All inputs need to be retrievable or excerpts of documents used should be Completion of the Reference Boxes is attached.

optional for all questions.

See site specific design input procedures for guidanre In identifying inputs.

Yes "

No a N/A Cl Verifier Comments:

Resolution:

Calculation Design Verification Checklist Page go of b.

Calc No.

PN PS-1-ERHS-ll.B-4 Entergy Revision 1

Sheet A1-3 of A1-6 Subiect: Control Room and Technical Support Center Accident y/'s Using ARCON96 - Calculation Design Verification I

2.

Assumptions - Have the assumptions been verified?

Where necessary, are assumptions identified for subsequent re-verification when the detailed activities are completed?

Page No.

OR Reference Yes F Verifier Comments:

No El N/A El Paragraph No.

Resolution:

Y

3.

Quality Assurance - Is the quality level correct?

Reference Page No.

OR Paragraph No.

Yes,

No a N/A El Verifier Comments:

d 4.

Resolution:

I

4.

Codes, Standards and Regulatory Requirements - Are the applicable codes, standards and regulatory requirements, including issue and addenda properly identified and are their requirements for design met?

Reference Page No.

OR Paragraph No.

Yes X No El N/A E Verifier Comments:

Resolution:

Calculation Design Verification Checklist Page.3 of 4.

Calc No.

PNPS-1-ERHS-lI.B-4

. Entergy Revision 1

Sheet A1-4 of A1-6 Subiect: Control Room and Technical Support Center Accident -/Q's Usin6 ARCON96 - Calculation Design Verification Y

5.

Construction and Operating Experience - Has applicable operating experience been considered?

Reference Page No.

OR Paragraph No.

Yes M No D N/A,

Verifier Comments:

Resolution:

I 6

Interfaces - Have the design interface requirements been 6

satisfied and documented?

Reference Page No.

OR Yes El No 0 N/A qr Paragraph No.

Verifier Comments:

It Resolution:

7.

Methods - Was an appropriate analytical method used?

Page No. _

OR Paragraph Nc Reference Yes 9 Verifier Comments:

No 0 N/A El sLaJc.

Resolution:

Calculation DesignVerification ChecklisttPage e of

Calc No.

PNPS-1-ERHSI-IS.B-4 Entergy Revision 1

Sheet Al-5 of A1-6.

Subject:

Control Room and Technical Support Center Accident 7/Q's Using ARCON96 - Calculation Design Verification

8.

Design Outputs - Is the output reasonable compared to the inputs?

Reference Page No.

OR Paragraph No.

Yes 0VI No El N/A El Verifier Comments:

C Resolution:

.7 9.

Acceptance Criteria - Are the acceptance criteria incorporated in the calculation sufficient to allow verification that design requirements have been satisfactorily accomplished?

Reference Page No.

OR Paragraph No.

Yes 0 Verifier Comments:

No El N/A I Resolution:

10.

Records and Documentation - Are requirements for record preparation, review, approval, retention, etc., adequately specified?

Are all documents prepared in a clear legible manner suitable for microfilming and/or other documentation storage method? Have all Impacted documents been identified for update?

Reference Page No.

OR Paragraph No.

Yes Xl Verifier Comments:

No El NIA El Resolution:

i n P g Calculation Design Verification Checklist Page a'of 4,5

Calc No.

PNPS-1-ERHS-I.B-4 Entergy Revision 1

Sheet A1-6 of A1-6.

Subiect: Control Room and Technical Support Center Accident Y/Q's Using ARCON96 - Calculation Design Verification

11.

Software Quality Assurance-For a calculation that utilized software applications (e.g., GOTHIC, SYMCORD), was it properly verified and validated in accordance with ENN IT-104 or previous site SQA Program?

Reference Page No.

OR Paragraph No.

Yes Verifier Comments:

No E N/A a Resolution:

OTHER COMMENTS RESOLUTIONS All comments for "NO" answers have been resolved satisfactorily.

Calculation Design Verification Checklist Page -

of to 2.04.003 Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Plant Proposed Amendment to the Technical Specifications Proposed Changes to the Pilgrim Technical Specifications Marked-Up and Insert Pages (13 pages)

TS Page 3/4.2-24 TS Page 3/4.7-11 TS Page 3/4.7-12 TS Page 3/4.7-13 TS Page 3/4.7-14 TS Page 3/4.7-15 TS Page 3/4.7-16 TS Bases Pages B3/4.7-1 0 B3/4.7-1 1 B3/4.7-1 2 Insert A to page B3/4.7-1 0 and Insert B to page B3/4.7-12 B3/4.7-1 3 Inserts C to page B3/4.7-13

I, 4

I I

PNPS TABLE 3.2.D RADIATION MONITORING SYSTEMS THAT INITIATE ANDIOR ISOLATE Minimum It of I

' Operable Instrument Channels Per TriP system (1)

Trip Function Trip Level Setting Action (2) 2 2

Refuel Area Exhaust Monitors Refuel Area Exhaust MVonitors Upscale, <100 mr/hr Downscale I

A or B A or B NOTES FOR TABLE 3.2.D

1.

Whenever the systems are required to be operable, there shall be two operable or tripped trip systems. If this cannot be met, the indicated action shall be taken.

2.

Action LOss-kt a.1 A.

Cease o eratio e re e

L-0e DteliV)

B.

Isolate ary co ainment and start I e standby gas treatment syste

,N A men ent N. 89-,47-2--

314.2-24

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont.)

A.

Primary Containment (Cont.)

With no H2 analyzer operable, reactor operation is allowed for up to AS hours. If one of the inoperable analyzers is not made fully operable within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , the reactor shaue be in at least Hot Shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.7 CONTAINMENT SySTEMS (Cont.)

B.

Slandbv Gas Treatment Si/stem and Control Room Hich Efficiency Air Filtration Svstem

1. Standby Gas Treatment System

a. Except as specified in 3.7.B.1.c or 3.7.B.1.e below, both trains of the standby gas treatment shall be operable when in the Run, Startup, and Hot Shutdown MODES. during {I movement ofdrraauated fuel assemblies in the secondary containment, ano curing movement o new uel ove the spent fuel pool, andtiuirg CRE LTRATIONS.

anal cuing operations with a potential for draining the reactor vessel (OPDRVs),

or the reactor shall-be in cold shutdown within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

b. 1. The results of the in-place' cold DOP tests on HEPA filters shall show >99°%° DOP removal. The results of halogenated hydrocarbon tests'on charcoal adsorber banks shall show

>99.9%0 halogenated hydrocarbon removal.

5. Standby Gas Treatment System and Control Room Hich Efficiencv Air Filtration Svstem

1. Standby Gas Treatment System

a. 1. At least once per operating cycle, it shall be demonstrated that pressure drop across the combined high efficiency filters and

~

charcoal adsorber banks is less than 8 inches of water at 4000 cfm.

9. At least once per operating cycle, demonstrate that the inlet heaters on each train-are operable and are capable of an output of at least 20 kW.

I

3. The tests and analysis of

-Specification 3.7.B.1.b. shall be performed at least once per operating cycle or following painting, fire or chemical release in any ventilation zone communicating with the system while the system is operating that could contaminate the HEPA filters or charcoal adsorbers.

4. At least once per operating cycle, automatic initiation of 1

4.

(Revision

444, 226 )

A mend ent 3M4.7-1 1

LIMITING CONDmONS FOR OPERATION SURVEILLANCE IRSOUIREMENTS 3.7 B.

1 CONTAINMENT SYSTEMS (Cont.)

Standbv Gas Treatment Systemn and Control Room Hiah Efficiencv Air Filtration System (Cont.)

b. 2. The results of the laboratory carbon sample analysis shall show each carbon adsorber bank is capable of >97.5% methyl iodide removal at 70% R.H. and 86'F. The carbon sample shall be obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978 and tested in accordance with ASTM D3803-1989. The analysis results are to be verified as acceptable within 31 days after sample removal, or declare that train inoperable and take the actions specified in 3.7.B.i.c.

-e. From and after the date that one train of the Standby Gas Treatment System is made or found to be inoperable for ahy reason, continued reactor operatio firradalted iue( lifiaiQ e

u

~fe fue succeeding seven days providing that within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months all active components of the other standby gas treatment train are verified to be operable and the diesel generator associated with the operable train is operable.

4.7 CONTAINMENT SYSTEMS (Cont.)

B. Standbv Gas Treatment System and Control Room Hiah Efficiency Air Filtration Svst em (Cont.)

each branch of the standby gas treatment system shall be demonstrated, with Specification 3.7.B.1.d satisfied.

Each train of the standby gas treatment system shall be operated for at least 15 minutes per month.

6. The tests and analysis of Specification 3.7.B.i.b.2 shall be performed after every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of

.system operation.

b. 1.in-place cold DOP testing shall be performed on the HEPA filters after each completed or partial replacement of the HEPA filter bank and after any structural maintenance on the HEPA filter system housing which could affect the HEPA filter bank bypass leakage.

2. Halogen ated hydrocarbon testing X shall be performed on the charcoal adsorber bank after each partial or complete replacement of the charcoal adsorber bank or after any structural maintenance on the.charcoal adsorber housing which could affect the charcoal adsorber bank bypass leakage.

If the system is not made fully operable within 7 days, reactor shutdown shall be initiated and the reactor shall be in cold shutdown within the next 36 hour^and fuel (handlingpera fi shell be termiated ithin2nho ro VFuel handling operations in progress

~) may be completed.

Amendment No. 12. 50; 52iGo, 14, 151, 16A, 1

'0

,~

3/4.7-12

LIMWTING CONDMONS FOR OPERA7TON SURVEILLANCE POUMENTS i,7 CONTA h T SYsris(Coot) 4.7 CONTAINMENTSYSTEMS (Cont.)

.taov Gas Tratment S and Control B.

StandbV Gas Treatment S d

nrol Room High Efficincv Air F]tiadon Syst-am In Hit Efficiincv Air Filtration System (Cont.)

(Cont.)

d, F=s siU opeate within : 10% of 4000 ch.

_c.

From and a:

the date tha one train Oithe Standby Gas Trenatent Sys=m L

~~is m-A or found to beinoperable for 7 tr s

~~ - l renieug operatznnsre pesmnussi c

/

i provdg that uithin 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months all Bi o4.2 QCLf As actve components of th-oth^r tain

_ +

are verincd to be operablz and the diesel generator associated with the operable train is operable.

If the systm is not made fuiuy operable within 7 days, i) pla ethe operable train in op:eraton immediately or ii) susped movement oa rrdiated U

fuel asscmblies in socondary containment r

fue talaiig

[F GAny fuel assembly movement in progress kSj;.. o4-5 rny b^ completed I..

13 Amendment Hc. 't C,

, E2. w: , V2. w.

3, lt 11 ',

-_3)4.743

-1

LIMITING CONDITIONS FOR OPERATION 3.7 CONTAINMENT SYSTEMS (Cont.)

B. Standby Gas Treatment Svstem and Control Room Hich Efficiencv Air Filtration System (Corn.)

2. Control Room Hioh Efficiency Air Filtration Svstem

2. Except as specified in Specification 3.7.B.2.c or 3.7.B.2.e below, both trains of the Control Room High Efficiency Air Filtration System used for the processing of inlet air to the control room under accident conditions shall be operable when in the Run, Startup, and Hot Shutdown MODES, during movement of irradiated fuel assemblies in the secondary containment

-a curing ove v

eoer the spent fuel pool, and durino O

ALTERsATIONS and during operations with a potential for draining the reactor vessel (OPDR Vs),

or the reactor shall be in cold shutdown within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

SURVEILLANCE REOUIREMENTS 4.7 CONTAINMENT SYSTEMS (Cont.)

B. Standbv Gas Treatment System and Control Room Hioh Efficiency Air Filtration 'System (Cont.)

2_ Control Room High Efficiency Air Filtration Svstem

a. At least once per operating cycle the pressure drop across each combined filter train shall be demonstrated to be less than 6 inches of water at 1 000 cfm or the calculated equivalent.

b.- 1. The tests and analysis of Specifications 3.7.B;2.b shall be performed once per operating cycle or following painting, fire or.

chemical release in any ventilation zone communicating with the system while the system is operating.

b. 1. The results of the in-place coid DOP tests on HEPA filters shall show >99% DOP removal. The results of the halogenated hydrocarbon tests on charcoal adsorber banks shall show 299.9%

halogenated hydrocarbon removal when test results ate extrapolated to the initiation of the test.

2. The results of the laboratory carbon sample analysis shall show v 97.5% methyl iodide removal at 70% R.H. and 860F. The carbon sample shall be obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1976 and tested in accordance with ASTM D3803-1989. The analysis results are to be verified as acceotable within 31 davs after sample removal, or declare that train inDperable and take the actions specified in 3.7.B.2.c.

Am

/

2. In-p'ace cold DOP testing shall he performed affer each complete or parial replacement of the HEPA filter bank or after any structural maintenance on the system housing which could affect the HEPA filter bank bypass leakage.

3. Halogenated hydrocarbon testiog shall be performed after each complete or partial replacement of the charcoal adsorber bank or after any structural maintenance on the system housing which could affect the charcoal adsorber bank bypass leakage.

4. Each train shall be operated with the heaters in asttomatic for at least 15 minutes every month.

i 3/4.7-14

LTMITINqG CONDITTIONS 1R OPERATIOMN 3.7 CONTAINMENT SYSTEMS (Coat.)

SURVEMLLANCE RFOTMEPEMENTS 4.7 COWNTAINUMNT SYSTEMS (Cant.) -

B.

Standby Gas-T reetrnt Svstrn and Control Room Hzih Efcinev Air Filtration Svstom (Cont.)

B.

StAndbv Gas Trma=t Svst-n and Control Room Hinh En-i-nca' Air Filtration Sv.jte (Coat.1 5,- The. 12 and analysis of CSpci~c:tioa 3.7.B.2.b.2 vhall be-peinfonned af zr nverv 072.0 h o u r o fryr ste--, m 1 o: I..Ara1.

.jjer~

I.

- rornn and *r :th: dz-- that one train of the Control Room I-flig Er5ciracy Air Filtration Syst::n is made or found to b-ino:>erabl: forranv rsason, rnetaor

&Opt:

t fiud su e g 7 days providing that uithin 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months all active cornponents of the other CREBAF tr': ae verified to be op-rabl-and the diene! generator associated vith the operable train is operable. If tk: syste:nn is not made fully orerable vithin 7 days, r=cr shutdown shall be initiated and the reactor shall be in cold shutdownw ithin the ncxt 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months an ci anrn op-ravons Sa ii t

i Ui hours. Fd-l. handling opraton n

rogress may be comple

..t [st cn-n pmr operaing cycie d e o n s t a t t h a t i n l et h e at e r s on. ech =rin arzr ope.rzble and c2ablt of an ou~tu of at lst= 14

d.

Pcrform an instrument functional tcst on the humidiats controlling the beaters onDX per optrating cycle.

e.. Fans shll oII rate within ' 1O% of

.1000 cfn.

e. From and after the date that on-,

train of fa: Control PRoom Mhig N

Eficstncy Air Filtradon Syst= is

/

,ecJ

)

rn-ad:. or found to b-: inop,:rablc for J i r c

a4

_cs onl ic-uring tne sue ding 7 days' providing that Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months all VsS$/.R-CoP R~sY acztiv components of the other train are verified to be onerabl:

and th: di='.l gnrator associzted with the operable train is op-rable.

If the system is not mad-. fully operable within 7 da-s, vi sion 19 d

314.7.1 1 I

LIMITING cONDrTIoNS FOR OPERATON SURNTULLANCEP-POUIREMEM 3.7 COMMIN ET SYSTEMS (Cont.)

4.7 COQ AlhETSYSTEMS (Coot.)

i) prfo=r surveillant 4.7.B.2.bA for td operable CPRHEA cv::y 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or.

R) suspend movmn=t o inuatcd fuel assemblies in secondar catinzf=L (o nw ruet nnding over th spen Anfue assembly movemr.=t in progress ray be comrpltted C. S==odzrv. C-antainmenrt C.

Seoodaiv Containmrnt I

1. Secondary containmet shall be OPERABLE ihe in the RunP, Stamsp and Hot Shutdowm MODES, during movement oi cdfu a~sus~bH= in tht s~nda conWtnX~

\\mot

~

R LddI CEMM ONS 1 durig opeatons wu n a potn-ai 0

ra ng tie rea:tor vessdl (OPDRVs).

1. Eah ru~ling outagt prior to rfucling, seondary con inmet capability shasll b d=*oanst-a-d to mairtzin 1/4 itch of vnter vazuum Und-r calnm vind (5 mpb) conditions ath z filter tain flow rc of not more than 4000 cr~n.

2. a-With Seondary Containment inop-,rabl-i-h= in the Run, Startur and Hot Shutdomn MODES, restor Secondry Containm0nt to OPERABLE rtwus %ithin 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b. Ruecd Acao and Completion Tmn-e of 2.2 not m, be in hot Shutdown in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

,N-Cold Shutdown within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

c. With S=ondary Containment operable during movemn-t o

£ ai+/-d ruel asse=meS in thX seondary containmn and tauring movEinem or new ruME o tver e

D fuel pool, and during CORE AL ntrATIONS during OPDRVs,

1. SUSDpd movemet ofrdatd fue assenbli:s in 5-he sendary containmuet.

spzat fuX-l pooL./

\\

~AND/

\\. SWDd CORE AI~r _?k4T1D-S.

A.Iniiaxe aion-to suspend OPDRVs.

evis on encriien 0

1 ;Pe-314.7-16

BASES:

314.7 CONTAINMENT SYSTEMS (Cont)

Tests of impregnated charcoal identical to that used in the filters indicate that a shelf life of five years leads to only minor decreases in methyl iodide removal efficiency. Hence, the frequency of laboratory carbon sample analysis is adequate to demonstrate acceptability. Since adsorbers must be removed to perform this analysis this frequency also nuinimizes the system out of service time as a result of surveillance testing. In addition, although the halogenated hydrocarbon testing is basically a leak test, the adsorbers have charcoal of known effinciency and holding capacity for elemental iodine and/or methyl iodide, the testing also gives an indication of the relative efficiency of the installed system. The 31 day requirement for the ascertaining of test results ensures that the ability of the charcoal to perform its designed function is demonstrated and known in a timely manner.

The required Standby Gas Treatment System flow rate is that flow, less than or equal to 4000 CFM which is needed to maintain the Reactor Building at a 0.25 inch of water negative pressure under calm wind conditions. This capability is adequately demonstrated during Secondary Containment Leak Rate Testing performed pursuant to Technical Specification 4.7.C.l.c.

The test frequencies are adequate to detect equipment deterioration prior to significant defects, but the tests are not frequent enough to load the filters or adsorbers, thus reducing their reserve capacity too quickly.

The filter testing is performed pursuant to appropriate procedures reviewed and approved by the

'-Operations Review Committee pursuant to Section 6 of these Technical Specifications. The in-place testing of charcoal filters is performed by injecting a halogenated hydrocarbon into the system upstream of the charcoal adsorbers. Measurements of the concentration upstream and downstream are made. The ratio of the inlet and outlet concentrations gives an overall indication of the leak tightness of the system. A similar procedure substituting dioctyl phthalate for halogenated hydrocarbon is used to test the HEPA filters.

Pressure drop tests across filter and adsorber banks are performed to detect plugging or leak paths though the filter or adsorber media. Considering the relatively short times the fans will be run for test purposes, plugging is unlikely and the test interval of once per operating cycle is reasonable.

System drains and housing gasket doors are designed such that any leakage would be inleakage from the Standby Gas Treatment System Room. This ensures that there will be no bypass of process air around the filters or adsorbers-.

Only one of the two Standby Gas Treatment Systems (SBGTS) is needed to maintain the secondary containment at a 0.25.inch of water negative pressure upon containment isolation. If one system is made or found to be inoperable, there is no immediate threat to the containment system performance and reactor operation or refueling activities may continue while repairs are being made. In the event one SBGTS is inoperable, the redundant system's active components will be verified to be operable within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . This substantiates the availability of the operable system and justifies continued reactor or refueling operations.

During refueling outages, if the inoperable train is not restored to operable status within the require completion time, the operable train should immediately be placed in operation. This action ensures that the remaining train is operable, that no failures that could prevent automatic actuation have occurred, and that any other failure would be readily detected. An alternative is to suspend fuel movement, thus, placing the plant in a condition that minimizes risk.

Revisionlf e

17B 314.7-10

BASES:

3/4;7 CONTAINMENT SYSTEMS (Cont) areGT is'p no required.nditio whr h

B.2 Control Room Hiah Efficiencv Air Filtration Svstem The Control Room High Efficiency Air Filtration System is designed to filter intake air for the control room atmosphere during conditions when normal intake air may be contaminated. Following manual'initiation, the Control Room High Efficiency Air Filtration System is designed to position dampers and start fans which divert the normal air flow through charcoal adsorbers before it reaches the control room.

High Efficiency Particulate Air (HEPA) filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers. The charcoal adsorbers are installed to reduce the potential intake of radioiodine to the control room. A second bank oftHEPA filters is installed downstream of the charcoal filter.

The in-place test results should indicate a system leak tightness of-less than 0.1 % bypass leakage for the charcoal adsorbers and a HEPA efficiency of at least 99% removal of cold DOP particulates. The laboratory carbon sample test results should indicate a methyl iodide removal'efficiency of at least 97.5% for expected accident conditions. Tests of impregnated charcoal identical to that used in the filters indicate that a shelf life of five years leads to only minor decreases in methyl iodine removal'efficiency. Hence, the frequency of laboratory carbon sample analysis is adequate to demonstrate acceptability.

Since adsorbers must be removed to perform this analysis, this frequency also minimizes the system out of service time as a result of surveillance testing. In addition, although the halogenated hydrocarbon testing is basically a leak test, the adsorbers have charcoal of known efficiency and holding capacity for eleniental iodine and/or methyl iodide, the testing also gives an indication of the relative efficiency of the installed system. The 31 day requirement for the ascertaining of test results ensures that the ability of the charcoal to perform its designed function is demonstrated and known in a timely manner.__

Determination of the system pressure drop once per operating cycle provides indication that the HEPA filters and charcoal adsorbers are not clogged by excessive amounts of foreign matter and that no bypass routes through the filters or adsorbers had developed.

Considering the relatively short times the systems will be operated for test purposes, plugging is unlikely and the test interval of once per operating cycle is reasonable.

B3/4.7-11

INSERT "A" TO PAGE B3/4.7-1 0 As discussed in Bases Section B3/4.7.C "Secondary Containment", SGTS is not required to be operable during movement of irradiated fuel assemblies that have been allowed to decay for the minimum specified decay period i.e., no longer 'recently irradiated.

During movement of recently irradiated fuel, if one train of SGTS is made or found to be inoperable and the inoperable train is not restored to operable status within the required completion time, the operable train should immediately be placed in operation. This action ensures that the remaining train is operable, that no failures that could prevent automatic actuation have occurred, and that any other failure would be readily detected. An alternative is to suspend movement of recently irradiated fuel, thus, placing the plant in a condition that minimizes risk. If both trains of SBGTS are inoperable, the plant is brought to a condition where the SBGTS is not required.

INSERT "B" TO PAGE B3/4.7-12 As discussed in Bases Section B3/4.7.C "Secondary Containment' CRHEAFS is not required to be operable during movement of irradiated fuel assemblies that have been allowed to decay for the minimum specified decy period i.e., no longer 'recently irradiated.

BASES:

3/4.7 CONTAINMENT SYSTEMS (Cont.)

B2 Control Room High Efficiency Air Filtration Systm (Cont.)

The test frequencies are adequate to detect equipment deterioration prior to significant defeCts, but the tests are not frequent enough to load the filters or adsorbers, thus reducing their reserve capacity too quickly.

The filter testing is performed pursuant to appropriate procedures reviewed and approved by the Operations Review Committee pursuant to Section 6 of these Technical Specifications. The in-place testing of charcoal filters is performed by injecting a halogenated hydrocarbon into the system upstrej of the charcoal adsorbers. Measurements of the concentration upstrean and downstream are made. The ratio of the inlet and outlet concentrations gives an overall indication of the leak tightness of the system. A similar procedure substituting dioctyl phithalate for halogenated hydrocarbon is used to test the HEPA fibers.

Air flow through the filters and charcoal adsorbers for 15 minutes each month assures operability ofthe system. Since the system heaters are automatically controlled, the air flowing through the filters and adsotbers will be 570% relative humidity and will have the desired drying efect If one train of the system is made or found to be inoperable, there is no immediate threat to the control room, and reactor operation or fuel handling may continue for a limited period of time while repairs are being made. In the event one CRHEAF train is inoperable, the redundant system's active components will be verified to be operable within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . During refueling outages, if the inoperable train is not restored to operable status within the required completion time, refueling operations may continue provided the operable CRHEAF train is placed in the pressurization mode daily. This action ensures that the remaining train is operable, that no failures that would prevent actuation will occur, and that any active failure will be readily detected. Anralternative is to suspend activities that present a potentiai for releasing radioactivity that might require isolation of the control room. If both trains of the CRHEAF system are inoperable, the reactor will be brought to a condition where the Control Room High Efficiency Air Filtration System is not required.

170 B314.7-12

BASES:

3/4.7 CONTAINMENT SYSTEMS (Cont)

C.

Secondarv Containment sf sthem secondary containme Is eusigned to allnime at d level release of radioact ve ll materials which might result from a serious accident. The reactor building provides secon containment during reactor operation, when the dryeell is sealed and in service. the rea br uildin provides primarl containment when the reactor is shutdown and the accidell is seop uring refueling. Because the secondary containment is an integral part of the complet ent smsteri, secondarm containment is required at all times that primary containment ias well as during refueling./

There are two principal accidents for which credit is taken for secondary coa ent operability Theseare alossofcoolantaccident (LOCA) and a fuel handlingaccidentoithe e[sncondary containment. The secondary containment performs no active finction i sponse to each of these lirniting events; however, its leak tightness is required to ensure that treease of radioactive

.materials forom the primaryv.containment is restricted to those lagaptsand associated leakage rates assumed in the accident analysis and that fission prout C

raped within the secondary containment structure will be treated by the SGT System priory discharge to the environment.

An operable secondary containment provides a control Volm ino which fission products that

.bpass or leak from primary containment, or are released om the reactor coolant pressure boundary components located in secondary containmen can be diluted and processed prior to release to the environment. For the secondary conta' ent to be considered operable, it must have adequate leak tightness to ensure that the required amcuum can be established and maintained.

If secondary containment is inoperable (when r ired to be operable), it must be'restored to operable statusithin 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months pletion time provides a period of time to correct the problem that is commensurate with the imp ce of maintaining secondary containment during Run, Startup, and Hot Shutdown modes.

s time period also ensures that the probability of an accident (requiring secondary containm it operability) occurring during periods where secondar containment is inoperable is minimal.

If secondary containment cannot b restored to operable status within the required completion time.

the plant must be brought to a m e in which the LCO does not apply. To achieve this status, the plant must be brought to at I Hot Shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to Cold Shutdown within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed complet n times are reasonable, based on operating experience, to reach the required plant conditions rn full power conditions in an orderly manner and without challenging plant systems.

Movement of irradiad fuel assemblies in the secondary containment, movement of new fuel over the spent fuel pool ore alterations, and OPDRVs can be postulated to cause fission product release to the sec ndary containment. In such cases, the secondary containment is the only barrier to release of fi ion products to the environment. Core alterations, movement of irradiated fuel assemblies, d movement of new fuel over the spent fuel pool must be immediately suspended if the secon

' containment is inoperable.

Suspen on of these activities shall not preclude completing an action that involves moving a corn ent to a safe position. Also, action must be immediately initiated to suspend OPDRVs to mIn ze the probability of a vessel draindown and subsequent potential for fission product release.

ctions must continue until OPDRVs are suspended.

Initiating reactor building isolation and operation of the standby gas treatment system to maintain at least a 1/4 inch of water negative pressure within the secondarv containment provides an adequate test of the operation of the reactor building isolation valves, leak tightness of the reactor building and performance of the standby gas treatment system. Functionally testing the initiating sensors and associated trip channels demonstrates the capability for automatic actuation.

Performing these tests prior to refueling will demonstrate secondary containment capability prior to the time the primary containment is opened for refueling. Periodic testing gives sufficient

,_qfidence of reactor building integrity and standby gas treatment system performance c~apability.

Rev i166sB34on B3/4.7 13

INSERT "C" TO PAGE B3/4.7-13 The secondary containment is designed to minimize any ground level release of radioactive materials that might result from a serious accident. The reactor building provides secondary containment during reactor operation, when the drywell is sealed and in service; the reactor building provides primary containment during periods when the reactor is shutdown, the drywell is open, and activities are ongoing that require secondary containment to be operable. Because the secondary containment is an integralpart of the complete containment system, secondary containment is required at all times that primary containment is required as well as during movement of 'recently irradiated" fuel and during operations with the potential to drain the reactor vessel (OPDRV).

There are two principal accidents for which credit is taken for secondary containment operability. These are a loss of coolant accident (LOCA) and a fuel handling accident involving "recently irradiated fuel. The secondary containment performs no active function in response to each of these limiting events; however, its leak tightness is required to ensure that the release of radioactive materials from primary containment is restricted to those leakage paths and associated leakage rates assumed in the accident analysis and that fission products entrapped within the secondary containment structure will be treated by the Standby Gas Treatment System (SGTS) prior to discharge to the environment.

In addition to these limiting accidents, OPDRVs can be postulated to cause a fission product release. During movement of recently irradiated fuel and OPDRVs, secondary containment would be the only barrier to a release to the environment. Therefore, movement of recently irradiated fuel and OPDRVs must be immediately suspended if the secondary containment is inoperable. Suspension of these activities shall not preclude completing an action that involves moving a component to a safe position. Also, action must be immediately initiated to suspend OPDRVs to minimize the probability of a vessel drain down and subsequent potential for fission product release. Actions must continue until OPDRVs are suspended.

An operable secondary containment provides a control volume into which fission products that bypass or leak from primary containment, or are released from the reactor coolant pressure boundary components located in secondar; containment can be diluted and processed prior to release to the environment. For the secondary containment to be considered operable, it must have adequate leak tightness to ensure that the required vacuum can be established and maintained.

If secondary containment is inoperable (when required to be operable), it must be restored to operable status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The 4-hour completion time provides a period of time to correct the problem that is commensurate with importance of maintaining secondary containment during Run, Startup, and Hot Shutdown modes. This time period also ensures that the probability of an accident (requiring secondary containment operability) occurring during periods where secondary containment is inoperable is minimal.

If secondary containment cannot be restored to operable status within the required completion time, the plant must be brought to a mode in which the LCO does not apply. To achieve this status during power operation, the plant must be brought to at least Hot Shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to Cold Shutdown within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed completion times are reasonable, based on operating experience, to reach the required plant conditions from full power condition in an orderly manner and without challenging plant systems.

The Fuel Handling Accident (FHA) analysis is based on 10 CFR 50.67 and R. G. 1.183 Alternate Source Term Methodology. This parametric analysis concluded that the calculated TEDE values to the control room occupants, the exclusion area boundary, and the low population zone are well below the allowable TEDE limits established in 10 CFR 50.67 without crediting Secondary Containment, SGTS and CRHEAFS as long as a the fuel is allowed to decay for at least 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months following reactor shutdown.

As a result, 'Recently irradiated" fuel is defined as fuel that has occupied part of a critical reactor core within the previous 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , i.e. reactor fuel that has decayed less than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months following reactor shutdown. Each fuelcycle, prior to the refueling outage, the decayperiod that must elapse prior to movement of irradiated fuel in the core will be re-evaluated to ensure the appropriate, minimum decayperiod is enforced to maintain the validity of the FHA dose consequence analysis.

Therefore, SGTS, CRHEAFS and Secondary Containment are not required to be operable during movement of decayed irradiated fuel that is no longer is considered 'recently irradiated". Conversely, Secondary Containment, SGTS, and CRHEAFS are required to be operable during movement of recently irradiated fuel assemblies to 2.04.003 Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Plant Proposed Amendment to the Technical Specifications Retyped Technical Specifications and Bases Pages (12 pages)

TS Page 3/4.2-24 TS Page 3/4.7-11 TS Page 3/4.7-12 TS Page 3/4.7-13 TS Page 3/4.7-14 TS Page 3/4.7-15 TS Page 3/4.7-16 TS Bases Pages 63/4.7-1 0 B3/4.7-1 1 63/4.7-12 63/4.7-13 63/4.7-14

PNPS TABLE 3.2.D RADIATION MONITORING SYSTEMS THAT INITIATE AND/OR ISOLATE Minimum # of Operable Instrument Channels Per Trip Svstem (1)

Trip Function Trip Level Settinq Action (2) 2 2

Refuel Area Exhaust Monitors Upscale, <100 mr/hr A or B Refuel Area Exhaust Monitors Downscale A or B NOTES FOR TABLE 3.2.D

1.

Whenever the systems are required to be operable, there shall be two operable or tripped trip systems. If this cannot be met, the indicated action shall be taken.

2.

Action A. Cease movement of recently irradiated fuel assemblies and operations with potential to drain the reactor vessel (OPDRVs).

B. Isolate secondary containment and start the standby gas treatment system during movement of recently irradiated fuel assemblies and operations with potential to drain the reactor vessel (OPDRVs).

Amendment No. 89, 1-72 314.2-24

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont.)

A.

Primary Containment (Cont.)

With no H2 analyzer operable, reactor operation is allowed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . If one of the inoperable analyzers is not made fully operable within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , the reactor shall be in at least Hot Shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.7 CONTAINMENT SYSTEMS (Cont.)

B. Standby Gas Treatment System and Control Room High Efficiency Air Filtration System

1. Standby Gas Treatment System

a. Except as specified in 3.7.B.1.c or 3.7.B.1.e below, both trains of the standby gas treatment shall be operable when in the Run, Startup, and Hot Shutdown MODES, during movement of recently irradiated fuel assemblies in the secondary containment, and during operations with a potential for draining the reactor vessel (OPDRVs),

B.

Standby Gas Treatment System and Control Room High Efficiency Air Filtration System

1. Standby Gas Treatment System

a. 1. At least once per operating cycle, it shall be demonstrated that pressure drop across the combined high efficiency filters and charcoal adsorber banks is less than 8 inches of water at 4000 cfm.

2. At least once per operating cycle, demonstrate that the inlet heaters on each train are operable and are capable of an output of at least 20 kW.

3. The tests and analysis of Specification 3.7.B.1.b. shall be performed at least once per operating cycle or following painting, fire or chemical release in any ventilation zone communicating with the system whie the system is operating that could contaminate the HEPA filters or charcoal adsorbers.

4. At least once per operating cycle, automatic initiation of or the reactor shall be in cold shutdown within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

b. 1. The results of the in-place cold DOP tests on HEPA filters shall show >99% DOP removal. The results of halogenated hydrocarbon tests on charcoal adsorber banks shall show

>99.9% halogenated hydrocarbon removal.

Amendment No. 15, 42,50, 51, 52,112,4,151, 161, 170, 187,4 3/4.7-1 1

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont.)

B.

Standby Gas Treatment System and Control Room High Efficiency Air Filtration System (Cont.)

b. 2. The results of the laboratory carbon sample analysis shall show each carbon adsorber bank is capable of >97.5% methyl iodide removal at 70% R.H. and 860F. The carbon sample shall be obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978 and tested in accordance with ASTM D3803-1989. The analysis results are to be verified as acceptable within 31 days after sample removal, or declare that train inoperable and take the actions specified in 3.7.B.1.c.

c. From and after the date that one train of the Standby Gas Treatment System is made or found to be inoperable for any reason, continued reactor operation is permissible only during the succeeding seven days providing that within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months all active components of the other standby gas treatment train are verified to be operable and the diesel generator associated with the operable train is operable.

4.7 CONTAINMENT SYSTEMS (Cont.)

B. Standby Gas Treatment System and Control Room High Efficiency Air Filtration System (Cont.)

each branch of the standby gas treatment system shall be demonstrated, with Specification 3.7.B.1.d satisfied.

5. Each train of the standby gas treatment system shall be operated for at least 15 minutes per month.

6. The tests and analysis of Specification 3.7.B.1.b.2 shall be performed after every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of system operation.

b. 1. In-place cold DOP testing shall be performed on the HEPA filters after each completed or partial replacement of the HEPA filter bank and after any structural maintenance on the HEPA filter system housing which could affect the HEPA filter bank bypass leakage.

2. Halogenated hydrocarbon testing shall be performed on the charcoal adsorber bank after each partial or complete replacement of the charcoal adsorber bank or after any structural maintenance on the charcoal adsorber housing which could affect the charcoal adsorber bank bypass leakage.

If the system is not made fully operable within 7 days, reactor shutdown shall be initiated and the reactor shall be in cold shutdown within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Amendment No.42,50,52,112,4 1, 151,6,17-0,187 3/4.7-12

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS (CONT) 4.7 CONTAINMENT SYSTEMS (Cont)

B. Standby Gas Treatment System and B. Standby Gas Treatment System and Control Room High Efficiencv Air Control Room High Efficiency Air Filtration System (Cont)

Filtration System (Cont)

d. Fans shall operate within t 10% of 4000 cfm.

e. From and after the date that one train of the Standby Gas Treatment System is made or found to be inoperable for any reason, movement of recently irradiated fuel assemblies and operations with a potential for draining the reactor vessel (OPDRVs) are permissible only during the succeeding 7 days providing that within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months all active components of the other train are verified to be operable and the diesel generator associated with the operable train is operable.

If the system is not made fully operable within 7 days, i) place the operable train in operation immediately OR ii) suspend movement of recently irradiated fuel assemblies in secondary containment and initiate actions to suspend OPDRVs. Any fuel assembly movement in progress may be completed.

Amendment No. 42, 50,51,.52,101,112,111,151, 161, 1703 3/4.7-1 3

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont.)

B. Standby Gas Treatment System and Control Room High Efficiency Air Filtration System (Cont.)

2. Control Room High Efficiency Air Filtration System 4.7 B.

CONTAINMENT SYSTEMS (Cont.)

Standby Gas Treatment System and Control Room High Efficiency Air Filtration System (Cont.)

2. Control Room High Efficiency Air Filtration System

a. Except as specified in Specification 3.7.B.2.c or 3.7.B.2.e below, both trains of the Control Room High Efficiency Air Filtration System used for the processing of inlet air to the control room under accident conditions shall be operable when in the Run, Startup, and Hot Shutdown MODES, during movement of recently irradiated fuel assemblies in the secondary containment, and during operations with a potential for draining the reactor vessel (OPDRVs),

or the reactor shall be in cold shutdown within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

a. At least once per operating cycle the pressure drop across each combined filter train shall be demonstrated to be less than 6 inches of water at 1000 cfm or the calculated equivalent.

b. 1. The tests and analysis of Specifications 3.7.B.2.b shall be performed once per operating cycle or following painting, fire or chemical release in any ventilation zone communicating with the system while the system is operating.

b. 1. The results of the in-place cold DOP tests on HEPA filters shall show 299% DOP removal. The results of the halogenated hydrocarbon tests on charcoal adsorber banks shall show 299.9%

halogenated hydrocarbon removal when test results are extrapolated to the initiation of the test.

2. The results of the laboratory carbon sample analysis shall show 297.5% methyl iodide removal at 70% R.H. and 861F. The carbon sample shall be obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978 and tested in accordance with ASTM D3803-1989. The analysis results are to be verified as acceptable within 31 days after sample removal, or declare that train inoperable and take the actions specified in 3.7.B.2.c.

2. In-place cold DOP testing shall be performed after each complete or partial replacement of the HEPA filter bank or after any structural maintenance on the system housing which could affect the HEPA filter bank bypass leakage.

3. Halogenated hydrocarbon testing shall be performed after each complete or partial replacement of the charcoal adsorber bank or after any structural maintenance on the system housing which could affect the charcoal adsorber bank bypass leakage.

4. Each train shall be operated with the heaters in automatic for at least 15 minutes every month.

Amendment No. 12, 50, 52, 112,111,151, 161, 170, 187 3/4.7-1 4

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS (CONT)

B. Standby Gas Treatment System and Control Room High Efficiency Air Filtration System (Cont)

c. From and after the date that one train of the Control Room High Efficiency Air Filtration System is made or found to be inoperable for any reason, reactor operation is permissible only during the succeeding 7 days providing that within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months all active components of the other CRHEAF train are verified to be operable and the diesel generator associated with the operable train is operable.

If the system is not made fully operable within 7 days, reactor shutdown shall be initiated and the reactor shall be in cold shutdown within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

d. Fans shall operate within +/- 10% of 1000 cfm.

e. From and after the date that one train of the Control Room High Efficiency Air Filtration System is made or found to be inoperable for any reason, movement of recently irradiated fuel assemblies and operations with a potential for draining the reactor vessel (OPDRVs) are permissible only during the succeeding 7 days providing that within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months all active components of the other train are verified to be operable and the diesel generator associated with the operable train is operable.

If the system is not made fully operable within 7 days, 4.7 CONTAINMENT SYSTEMS (Cont)

B. Standby Gas Treatment System and Control Room High Efficiency Air Filtration System (Cont)

5. The test and analysis of Specification 3.7.B.2.b.2 shall be performed after every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of system operation.

c. At least once per operating cycle demonstrate that the inlet heaters on each train are operable and capable of an output of at least 14 kw.

d. Perform an instrument functional test on the humidistats controlling the heaters once per operating cycle Amendment No. 12, 50, 51, 57,112,111,151,161,170 3/4.7-1 5

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS (CONT) 4.7 CONTAINMENT SYSTEMS (Cont) i)

perform surveillance 4.7.B.2.b.4 for the operable CRHEAF every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR C.

ii) suspend movement of recently irradiated fuel assemblies in secondary containment and initiate actions to suspend OPDRVs. Any fuel assembly movement in progress may be completed.

Secondary Containment

1. Secondary containment shall be OPERABLE when in the Run, Startup and Hot Shutdown MODES, during movement of recently irradiated fuel assemblies in the secondary containment, and during operations with a potential for draining the reactor vessel (OPDRVs).

2. a.With Secondary Containment inoperable when in the Run, Startup and Hot Shutdown MODES, restore Secondary Containment to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b. Required Action and Completion Time of 2.a not met, be in HOT Shutdown in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND Cold Shutdown within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

c. With Secondary Containment inoperable during movement of recently irradiated fuel assemblies in the secondary containment and during OPDRVs, immediately:

1. Suspend movement of recently irradiated fuel assemblies in the secondary containment.

AND

2. Initiate actions to suspend OPDRVs.

C.

Secondary Containment

1. Each refueling outage prior to refueling, secondary containment capability shall be demonstrated to maintain 1/4 inch of water vacuum under calm wind (5 mph) conditions with a filter train flow rate of not more than 4000 cfm.

I I

I Amendment No. 0, 161, 166, 170 3/4.7-1 6

BASES:

3/4.7 CONTAINMENT SYSTEMS (Cont)

B.1 Standby Gas Treatment System (Cont)

Tests of impregnated charcoal identical to that used in the filters indicate that a shelf life of five years leads to only minor decreases in methyl iodide removal efficiency.

Hence, the frequency of laboratory carbon sample analysis is adequate to demonstrate acceptability. Since adsorbers must be removed to perform this analysis this frequency also minimizes the system out of service time as a result of surveillance testing. In addition, although the halogenated hydrocarbon testing is basically a leak test, the adsorbers have charcoal of known efficiency and holding capacity for elemental iodine and/or methyl iodide, the testing also gives an indication of the relative efficiency of the installed system. The 31 day requirement for the ascertaining of test results ensures that the ability of the charcoal to perform its designed function is demonstrated and known in a timely manner.

The required Standby Gas Treatment System flow rate is that flow, less than or equal to 4000 CFM which is needed to maintain the Reactor Building at a 0.25 inch of water negative pressure under calm wind conditions. This capability is adequately demonstrated during Secondary Containment Leak Rate Testing performed pursuant to Technical Specification 4.7.C.1.c.

The test frequencies are adequate to detect equipment deterioration prior to significant defects, but the tests are not frequent enough to load the filters or adsorbers, thus reducing their reserve capacity too quickly. The filter testing is performed pursuant to appropriate procedures reviewed and approved by the Operations Review Committee pursuant to Section 6 of these Technical Specifications. The in-place testing of charcoal filters is performed by injecting a halogenated hydrocarbon into the system upstream of the charcoal adsorbers. Measurements of the concentration upstream and downstream are made. The ratio of the inlet and outlet concentrations gives an overall indication of the leak tightness of the system. A similar procedure substituting dioctyl phthalate for halogenated hydrocarbon is used to test the HEPA filters.

Pressure drop tests across filter and adsorber banks are performed to detect plugging or leak paths though the filter or adsorber media. Considering the relatively short times the fans will be run for test purposes, plugging is unlikely and the test interval of once per operating cycle is reasonable.

System drains and housing gasket doors are designed such that any leakage would be inleakage from the Standby Gas Treatment System Room. This ensures that there will be no bypass of process air around the filters or adsorbers.

Only one of the two Standby Gas Treatment Systems (SBGTS) is needed to maintain the secondary containment at a 0.25 inch of water negative pressure upon containment isolation. If one system is made or found to be inoperable, there is no immediate threat to the containment system performance and reactor operation or refueling activities may continue while repairs are being made. In the event one SBGTS is inoperable, the redundant system's active components will be verified to be operable within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . This substantiates the availability of the operable system and justifies continued reactor or refueling operations.

As discussed in Bases Section B3/4.7.C "Secondary Containment", SGTS is not required to be operable during movement of irradiated fuel assemblies that have been allowed to decay for the minimum specified decay period i.e., no longer "recently irradiated".

Revision B3/4.7-1 0

BASES:

314.7 CONTAINMENT SYSTEMS (Cont)

B.1 Standby Gas Treatment System (Cont)

During movement of recently irradiated fuel, if one train of SGTS is made or found to be inoperable and the inoperable train is not restored to operable status within the required completion time, the operable train should immediately be placed in operation.

This action ensures that the remaining train is operable, that no failures that could prevent automatic actuation have occurred, and that any other failure would be readily detected. An alternative is to suspend movement of recently irradiated fuel, thus, placing the plant in a condition that minimizes risk. If both trains of SBGTS are inoperable, the plant is brought to a condition where the SBGTS is not required.

B.2 Control Room High Efficiency Air Filtration System The Control Room High Efficiency Air Filtration System is designed to filter intake air for the control room atmosphere during conditions when normal intake air may be contaminated. Following manual initiation, the Control Room High Efficiency Air Filtration System is designed to position dampers and start fans which divert the normal air flow through charcoal adsorbers before it reaches the control room.

High Efficiency Particulate Air (HEPA) filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers. The charcoal adsorbers are installed to reduce the potential intake of radioiodine to the control room. A second bank of HEPA filters is installed downstream of the charcoal filter.

The in-place test results should indicate a system leak tightness of less than 0.1%

bypass leakage for the charcoal adsorbers and a HEPA efficiency of at least 99%

removal of cold DOP particulates. The laboratory carbon sample test results should indicate a methyl iodide removal efficiency of at least 97.5% for expected accident conditions. Tests of impregnated charcoal identical to that used in the filters indicate that a shelf life of five years leads to only minor decreases in methyl iodine removal efficiency. Hence, the frequency of laboratory carbon sample analysis is adequate to demonstrate acceptability. Since adsorbers must be removed to perform this analysis, this frequency also minimizes the system out of service time as a result of surveillance testing. In addition, although the halogenated hydrocarbon testing is basically a leak test, the adsorbers have charcoal of known efficiency and holding capacity for elemental iodine and/or methyl iodide, the testing also gives an indication of the relative efficiency of the installed system. The 31-day requirement for the ascertaining of test results ensures that the ability of the charcoal to perform its designed function is demonstrated and known in a timely manner.

Determination of the system pressure drop once per operating cycle provides indication that the HEPA filters and charcoal adsorbers are not clogged by excessive amounts of foreign matter and that no bypass routes through the filters or adsorbers had developed. Considering the relatively short times the systems will be operated for test purposes, plugging is unlikely and the test interval of once per operating cycle is reasonable.

The test frequencies are adequate to detect equipment deterioration prior to significant defects, but the tests are not frequent enough to load the filters or adsorbers, thus reducing their reserve capacity too quickly. The filter testing is performed pursuant to appropriate procedures reviewed and approved by the Operations Review Committee pursuant to Section 6 of these Technical Specifications. The in-place testing of charcoal filters is performed by injecting a halogenated hydrocarbon into the system upstream of the charcoal adsorbers. Measurements of the concentration upstream and Revision B3/4.7-1 1

BASES:

3/4.7 CONTAINMENT SYSTEMS (Cont) downstream are made. The ratio of the inlet and outlet concentrations gives an overall indication of the leak tightness of the system. A similar procedure substituting dioctyl phthalate for halogenated hydrocarbon is used to test the HEPA filters.

B.2 Control Room High Efficiency Air Filtration System (Cont)

Air flow through the filters and charcoal adsorbers for 15 minutes each month assures operability of the system. Since the system heaters are automatically controlled, the air flowing through the filters and adsorbers will be <70% relative humidity and will have the desired drying effect.

If one train of the system is made or found to be inoperable, there is no immediate threat to the control room, and reactor operation may continue for a limited period of time while repairs are being made. In the event one CRHEAF train is inoperable, the redundant system's active components will be verified to be operable within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . During movement of recently irradiated fuel in a refueling outage, if the inoperable train is not restored to operable status within the required completion time, movement of recently irradiated fuel may continue provided the operable CRHEAF train is placed in the pressurization mode daily. This action ensures that the remaining train is operable, that no failures that would prevent actuation will occur, and that any active failure will be readily detected. An alternative is to suspend movement of recently irradiated fuel. If both trains of the CRHEAF system are inoperable, the reactor will be brought to a condition where the Control Room High Efficiency Air Filtration System is not required.

As discussed in Bases Section B314.7.C 'Secondary Containment', CRHEAFS is not required to be operable during movement of irradiated fuel assemblies that have been allowed to decay for the minimum specified decay period i.e., no longer urecently irradiated".

C. Secondary Containment The secondary containment is designed to minimize any ground level release of radioactive materials that might result from a serious accident. The reactor building provides secondary containment during reactor operation, when the drywell is sealed and in service; the reactor building provides primary containment during periods when the reactor is shutdown, the drywell is open, and activities are ongoing that require secondary containment to be operable. Because the secondary containment is an integral part of the complete containment system, secondary containment is required at all times that primary containment is required as well as during movement of "recently irradiated" fuel and during operations with the potential to drain the reactor vessel (OPDRVs).

There are two principal accidents for which credit is taken for secondary containment operability. These are a loss of coolant accident (LOCA) and a fuel handling accident involving "recently irradiated" fuel. The secondary containment performs no active function in response to each of these limiting events; however, its leak tightness is required to ensure that the release of radioactive materials from primary containment is restricted to those leakage paths and associated leakage rates assumed in the accident analysis and that fission products entrapped within the secondary containment structure will be treated by the Standby Gas Treatment System (SGTS) prior to discharge to the environment.

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In addition to these limiting accidents, OPDRVs can be postulated to cause a fission product release. Duiing movement of recently irradiated fuel and OPDRVs, secondary containment would be the only barrier to a release to the environment. Therefore, movement of recently irradiated fuel and OPDRVs must be immediately suspended if the secondary containment is inoperable. Suspension of these activities shall not preclude completing an action that involves moving a component to a safe position.

C.

Secondary Containment (Cont)

Also, action must be immediately initiated to suspend OPDRVs to minimize the probability of a vessel drain down and subsequent potential for fission product release.

Actions must continue until OPDRVs are suspended.

An operable secondary containment provides a control volume into which fission products that bypass or leak from primary containment, or are released from the reactor coolant pressure boundary components located in secondary containment can be diluted and processed prior to release to the environment. For the secondary containment to be considered operable, it must have adequate leak tightness to ensure that the required vacuum can be established and maintained.

If secondary containment is inoperable (when required to be operable), it must be restored to operable status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months completion time provides a period of time to correct the problem that is commensurate with importance of maintaining secondary containment during Run, Startup, and Hot Shutdown modes.

This time period also ensures that the probability of an accident (requiring secondary containment operability) occurring during periods where secondary containment is inoperable is minimal.

If secondary containment cannot be restored to operable status within the required completion time, the plant must be brought to a mode in which the LCO does not apply.

To achieve this status during power operation, the plant must be brought to at least Hot Shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to Cold Shutdown within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed completion times are reasonable, based on operating experience, to reach the required plant conditions from full power condition in an orderly manner and without challenging plant systems.

The Fuel Handling Accident (FHA) analysis is based on 10 CFR 50.67 and R.G.

1.183 Alternate Source Term Methodology. This parametric analysis concluded that the calculated TEDE values to the control room occupants, the exclusion area boundary, and the low population zone are well below the allowable TEDE limits established in 10 CFR 50.67 without crediting Secondary Containment, SGTS and CRHEAFS as long as a the fuel is allowed to decay for at least 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months following reactor shutdown.

As a result, "recently irradiated" fuel is defined as fuel that has occupied part of a critical reactor core within the previous 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , i.e. reactor fuel that has decayed less than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months following reactor shutdown. Each fuel cycle, prior to the refueling outage, the decay period that must elapse prior to movement of irradiated fuel in the core will be re-evaluated to ensure the appropriate, minimum decay period is enforced to maintain the validity of the FHA dose consequence analysis.

Therefore, SGTS, CRHEAFS, and Secondary Containment are not required to be operable during movement of decayed irradiated fuel that is no longer is considered urecently irradiated". Conversely, Secondary Containment, SGTS, and CRHEAFS are required to be operable during movement of recently irradiated fuel assemblies.

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3/4.7 CONTAINMENT SYSTEMS (Cont)

Initiating reactor building isolation and operation of the standby gas treatment system to maintain at least a 1/4 inch of water negative pressure within the secondary containment provides an adequate test of the operation of the reactor building isolation valves, leak tightness of the reactor building and performance of the standby gas treatment system.

Functionally testing the initiating sensors and associated trip channels demonstrates the capability for automatic actuation. Performing these tests prior to refueling will demonstrate secondary containment capability prior to the time the primary containment is opened for refueling. Periodic testing gives sufficient confidence of reactor building integrity and standby gas treatment system performance capability.

Revision sB3/4.7-1 4 to 2.04.003 Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Plant Proposed Amendment to the Technical Specifications Summary of Commitments Commitment ID Description Due Date

1.

Entergy will revise the Pilgrim guidelines for assessing Completed prior to systems removed from service during the handling of the implementation non-recently irradiated fuel assemblies or core of this license alterations to implement the provisions of Section amendment.

11.3.6.5 of NUMARC 93-01, Revision 3.

2.

Revise Pilgrim UFSAR to reflect revised fuel handling Completed in analyses and alternate source term.

accordance with next scheduled FSAR update after approval of this application.

ML041130107

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