ML20045H538

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Procedure 8.7.3,Secondary Containment Leak Rate Test.
ML20045H538
Person / Time
Site: Pilgrim
Issue date: 01/29/1993
From:
BOSTON EDISON CO.
To:
Shared Package
ML20045H537 List:
References
NUDOCS 9307200344
Download: ML20045H538 (24)
v • d • e


Text

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i BOSTON EDISON RTYPE H6.08 PILGRIM NUCLEAR POWER STATION Procedure No. 8.7.3 SECONDARY CONTAINHENT LEAK RATE TEST IMPO!T"% TION r 17 Use restricted to reference REVIEN NS AND APPROVERS

,V Procedure Hr1ter N D 14 f Da'te

~, 0 0

/ technical Reviewer M , Date

<'~7Ef %f3bhy _

Validator Dafe h Procedure Owner n Y5D)?2

( date HSTP RELATED d /-42-93

'OAD Manaaer Date I QC REVIEW REQUIRED  !

h

// ORC Chairman t/;t? /93 Dafe i

ORC REVIEH REQUIRED / l

""^"'""D ll / /gl,p f~ l 9. fj l

SAFETY REVIEWapcIn:D/. ~ Restfonfible Manaaer Date NOT REQUIRED Effective Date: 1- % -9 A 9307200344 930712 ps 8.7.3 Rev. 29 PDR ADOCK 05000293  :

P PDR y i

. REVISION LOG

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Editorial 29A Date Originated 7/93 Pa_aes Affected Descriotion 16 Add "approximately" under (g) to maintain consistency with Tech Spec Table 6.9.1 Note 2.

REVISION 29 Date Originated 9/91 Paaes Affected Description 6 Provide documentation of test validity up to ambient wind speeds of 15 MPH. (RFI 91-483, NED 84-38) 4,7-11,18-21 Incorporate Main Control Room Panel Label Nomenclature changes in accordance with PDC 87-78F.

3,5,6 Add Section 3.0 (Definitions) and resequence sections 5.0 to 7.0 IAW PNPS 1.3.4-1.

REVISION 28 Date Originated 9/91 Paaes Affected Description 5,7-9,12-14 Removed requirement to inspect idle traincore plate D/P instruments per PDC 86-70.

Editorial Date Originated 4/91 I Paaes Affected Description 4,9 Add PNPS 2.2.125.1 to References and delete retired PNPS 2.4.147.  !

REVISION 27 Date Originated 4/91 '

Paaes Affected Description 4,15 To address and correct a problem identified by RFI 89-275 and ref. applicable section of Tech. Spec. after step and in Ref.

section.

8.7.3 Rev. 29 Page 2 of 23

TABLE OF CONTENTS EiL91 1.0 PURPOSE 4-

2.0 REFERENCES

4 -

3.0 DEFINITIONS 5 4.0 DISCUSSION 5 5.0 SPECIAL TOOLS AND EQUIPMENT 5 6.0 PRECAUTIONS AND LIMITATIONS 5 7.0 PREREQUISITES 6 8.0 PROCEDURE 7 ,

9.0 ACCEPTANCE CRITERIA 11 10.0 ATTACHMENTS 11 ATTACHMENT 1 - SECONDARY CONTAINHENT LEAK RATE SIGNOFF 12 ATTACHMENT 2 - SECONDARY CONTAINHENT CHECK-OFF (BY ELEVATION) 17 ATTACHMENT 3 - SGTS "A" AIR FLOW VS PERFORATED PLATE AP 22 ATTACHMENT 4 - SGTS "B" AIR FLOW VS PERFORATED PLATE AP 23 l

8.7.3 Rev. 29 Page 3 of 23 j

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! 1.0 PURPOSE This Procedure provides instructions for performing the secondary containment leak rate test.

2.0 REFERENCES

[1] FSAR, Section 5.3

[2] PNPS Procedures (a) 2.2.50, " Standby Gas Treatment" (b) 8.7.3.1, " Inspection of Secondary Containment Dampers" (c) 2.2.125.1, " Primary and Secondary Containment Isolation Reset"

[3] PNPS Technical Specification Section 4.7.C.1.c, Table 6.9.1

[4] P& ids (a) H-280, Heating and Ventilation I

(b) P&ID H-287, Plant Ventilation

'(c) P&ID H-321, Fan Room No. 1 (d) P&ID H-322, H&V and AC Fan Room No. 3 and 2 (e) P&ID H-323. H&V and AC Temperature Controls

[5] NOP-8301, Conduct of Operations

[6] NED Hemo #84-038, corresponds to FS&MC Hemo #84-015

[7] Vendor Manual V-0529, Pacific Air Products

[8] Design Changes (a) PDC 85-14, Reactor Building Secondary Containment Isolation Dampers (b) PDC 86-70, Standby Gas Treatment System Hodifications (c) PDC 88-53, Reactor Building Trucklock Door Mechanical Seal

[9] NRC resolved concern, UNR 83-23-02

[10] PCAQ NED 88-165

[11] PDC 87-78F, " Improvements to Labels, Nameplates on Main Control Room Panels" 8.7.3 Rev. 29 ,

Page 4 of 23

3.0 DEFINITIONS None 4.0 DISCUSSION This Procedure should be performed at each refueling outage prior to refueling as required by PHPS Technical Spccification 4.7.C.I.c, or as required for post work testing.

5.0 SPECIAL TOOLS AND EOUIPMENT

[1] Key for test switches

[2] Communications equipment 6.0 PRECAUTIONS AND LIMITATIONS

[1] Do not draw over 1" H2O vacuum across the Reactor Building.

[2] If this test is performed during reactor power operation, do not keep the Reactor Building isolated longer than 10 minutes as the main steam tunnel temperature will start to rise.

[3] A reading to the right of zero (downward) on the manometers is.

negative.

[4] An individual base line reading outside of 0 (-0.1 to +0.1)" H O2 indicates test results could be influenced and test should not be conducted until condition is corrected.

8.7.3 Rev. 29 Page 5 of 23

7.0 PREREOUISITES

[1] NHE's permission to perform test.

fiDIE The Turbine Building should be at a slight negative pressure (-0.1 to

-0.2 inches H 20) with respect to atmosphere as read on the manometers next to Panel C60.

[2] Turbine Building H&V System operating with 2 exhaust and 2 supply fans in service. Roof exhausters in operation as required.

[3] DPI-AA-22 and DPI-AA-32 calibrated and initially reading 0" H 20.

[4] At least one door at each access closed. ,

[5] Standby Gas Treatment System operable.

[6] All automatic ventilation system isolation dampers operable or secured in the isolated condition.

[7] All manometers filled and zeroed.

[8] Secondary containment checkoff (Attachment 2) considered and accepted.

[9] Specific purpose for test performance to be noted in Attachment 1.

[10] Hind speed is less than or equal to 15 MPH.

Additional testing was performed during the first operating cycle under various wind conditions to enable valid extrapolation of test results. (See LOC 0120 1035 for an example.)

NED performed an evaluation of PNPS 8.7.3, Revision 12, in early 1984 (FSLHC 84-015) which was transmitted by Hemo NED 84-38 (LOC 1468-0852). The evaluation found that the Procedure was adequate and that the practice of obtaining baseline readings and utilizing them to correct for initial conditions is valid provided that the baseline readings are kept within certain limits. These values should not be exceeded at wind speeds equal to or less than 15 HPH. The memo (NED 84-38) presents conclusions from the evaluation to establish the baseline data limits.

8.7.3 Rev. 29 Page 6 of 23

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l 8.0 . PROCEDURE .;

PERFORM'the test as follows:

[1] RECORD ambient conditions.  !

[2] VERIFY QR POSITION as required the SGTS as follows: i TRAIN A POSITION TRAIN B . POSITION. L (a) A0-N-99 TRAIN A A0-N-106, TRAIN.B' l INLET DMPR AUTO- INLET DMPR- AUTO (AO-N-108,. TRAIN A (AO-N-112, TRAIN B- ~

OUTL DMPR) (CLOSED) OUTL DNPR) (CLOSED) i I

(b) A0-N-135, OUTLET A0-N-135,~0VTLET CROSS CONNECT CROSS CONNECT DAMPER OPEN DAMPER OPEN (AO-N-136, INLET (AO-N-136. INLET CROSS CONNECT CROSS CONNECT DAMPER) (OPEN) DAMPER) (OPEN)

(c) A0-N-98, CONTAMINATED A0-N-101, REFUEL FLR EXH PLENUM DMPR AUTO EXH PLENUM DAMPER AUTO (AO-N-138, REFUEL FLR (AO-N-137, CONTAMINATED EXH DIVERT DNPR)- (CLOSED):

EXH DIVERT DNPR) (CLOSED)

[3] CLOSE the outer Reactor Building Trucklock door AND INFLATE.the seal. l

[4] OPEN the inner Reactor Building Trucklock door.

[5] PLACE hand switches.for both STANDBY GAS FANS A and B, VEX-210A and VEX-210B (Panel C7), in the "0FF" position.

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8.7.3 Rev. 29 Page 7 of 23

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I 8.0 PROCEDURE (Continued)

HDlf When the test switches are tripped, the signal will seal in and the Reactor Building will remain isolated. The SGTS fans will.not start until manipulated by this Procedure. An SGTS trouble alarm may come in and not reset until completion of this' test.

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[6] SIMULTANEOUSLY TURN both keylocked secondary containment isolation system initiation control switches (RPHA/CS and RPNB/CS on  :

Panel C7) to the " TEST" position.

(a) ALLOW 3 minutes for stabilization &ND TAKE base readings on the four manometers in the Reactor Building elevation 91',

6HD the two manometers in the Turbine Building elevation 51'.

(b) RECORD data on. Attachment 1 6MQ REVIEN that average baseline ,

is within bounds. [0 (-0.1 to +0.1)" H 20]

[7] AFTER noting which fans were operating, TURN all Reactor Building fan switches on~ Panel C61 to the "0FF" position.

[8] PLACE the fan control switch (on Panel C7) for VEX-210A (STANDBY 1 GAS FAN A) in the "AUT0"' position. LEAVE the control switch for the STANDBY GAS FAN B in the "0FF" position. k  :

[9] VERIFY dampers AD-N-99 &MQ A0-N-108 reposition to the OPEN position. ,

[10] REGULATE MO-N-109 as required such that flow is maximized but does  ;

not exceed 4000 CFM.

[11] ALLOW the manometers to stabilize &ND RECORD the approximate time '

necessary for stabilization on Attachment 1.

[12] RE00RD the following data on Attachment 1:

(a) Manometer AP readings.

(b) DP-AA-22 AP (c) FI-8126/8127, STANDBY GAS TREATHENT 00MHON OUTLET FLOW Indicators

[13] PLACE the fan control switch (on Panel C7) for VEX-210A (STANDBY GAS FAN A) in the "0FF" position.

[14] CLOSE the inner Reactor Building Trucklock door but QQ NQI INFLATE the seal. [PCAQ NED 88-165]

8.7.3 Rev. 29 Page 8 of 23 1

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8.0 PROCEDURE (Continued):

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[15] OPEN the outer Reactor Building Trucklock door. [PCAQ NED'88-165]

[16] PLACE the fan control switch (on Panel C7) for VEX-210A (STANDBY-GAS FAN A).in the "AUT0" position. LEAVE the control switch for

[  :

the STANDBY GAS FAN B in the "0FF" position. ,

[17] REGULATE MO-N-109 (STANDBY GAS FAN A OUTLET DAMPER)'as' required -

such that flow is maximized, but does not exceed 4000 CFM.

[18] ALLOW the manometers to stabilize MD RECORD the approximate time necessary for stabilization on Attachment 1.

[19] RECORD the following data on Attachment 1:

(a) Manometer AP readings (b) DP-AA-22 AP (c) FI-8126/8127 STANDBY GAS TREATMENT COMMON OUTLET FLOH Indicators

[20] PLACE the fan control switch (on Panel C7) for VEX-210A (STANDBY GAS FAN A) in the "0FF" position. ,

[21] VERIFY the damper control switches (on Panel C7) for A0-N-99 (TRAIN A INLET DMPR) AND A0-N-108 (TRAIN A OUTL DMPR) in the "AUT0" position and the dampers indicate CLOSED.

[22] PLACE the fan contro1' switch (on Panel C7)'for VEX-210B (STANDBY GAS FAN B) in the " MAINTENANCE" position. LEAVE the control 3 switch for the STANDBY GAS FAN A in the "0FF" position.

[23] VERIFY dampers A0-N-106 (TRAIN B INLET DMPR) MQ A0-N-112 (TRAIN B OUTL DMPR) reposition to the OPEN position.

[24] REGULATE MO-N-113 (STANDBY CAS FAN B OUTLET DAMPER) as required such that flow is maximized but does not exceed 4000 CFM.

[25] ALLOH the manometers to stabilize MD RECORD the approximate time necessary for stabilization on Attachment 1.

[26] RECORD the following data on Attachment 1; i (a) Manometer AP readings (b) DP-AA-32 AP (c) FI-8126/8127, STANDBY GAS TREATMENT COMMON OUTLET FLOH l Indicators l

[27] PLACE the fan control switch (on Panel C7) for VEX-210B (STANDBY GAS FAN B) in the "0FF" position.

l 8.7.3 Rev. 29 Page 9 of 23 4

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-l 8.0 PROCEDURE (Continued) j

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[28] CLOSE the outer Reactor Building Trucklock door &MQ INFLATE the I seal.

[29] OPEN the inner Reactor Building Trucklock ~ door.

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[30] PLACE the fan control switch (on Panel C7) for VEX-210B (STANDBY GAS FAN B) in the "HAINTENANCE" position. LEAVE.the control switch for the STANDBY GAS FAN A in the "0FF" position. i J

[31] REGULATE HO-N-113 (STANDBY GAS FAN B OUTLET-DAMPER) as required such that flow is maximized but does not exceed 4000 CFM.

[32] ALLON the' manometers to stabilize &ND RECORD the approximate time necessary for stabilization on Attachment 1.

t

[33] RECORD the following data on Attachment 1:

(a) Hanometer AP readings 1

(b) DP-AA-32 AP (c) FI-8126/8127, STANDBY GAS TREATHENT COMMON OUTLET FLOW Indicators l

[34] PLACE the fan control switch (on Panel C7) for VEX-210B (STANDBY GAS FAN B) in the "0FF" position. ,

[35] RESET _the secondary containment isolation in accordance with PNPS 2.2.125.1.

[36] RETURN the SGTS to normal line-up in'accordance with PNPS 2.2.50.

NOTE Independent verification may be performed by:

a. Direct method - checking appropriate equipment and/or controls QB l
b. Indirect method - observation of indicators and/or status lights An independent verification need not be performed if a person has the potential of receiving greater than 25 mrem whole body while performing the verification.

[37] VERIFY all components are returned to normal (Independent verification required).

i 8.7.3 Rev. 29 '!

Page 10 of 23

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8.0 EEQCEDURE (Continued) .

-[383-Documentation -i (a) ENTER the performance of the test in the Control Room Log.

(b) COMPLETE the signoff sheet &N._Q FORMARD to the Compliance Engineer.

(c) ROUTE to Control Room Annex for filing.

9.0 ACCEPTANCE CRITERIA

[1] The test was performed as written with no unexplained discrepancies.

[2] The individual Base:Line Readings were equal to

  • O (-0.1 to +0.1)" H20.

[3] A 1/4" water vacuum (average corrected value) on the secondary containment obtained with a filter train flow rate of eaual-to or less than 4000 CFM as determined from the perforated plate readings (DPI-AA-22/DPI-AA-32).

[4] That FIs 8126 and 8127 (STANDBY GAS TREATMENT COMMON OUTLET FLOW Indicators) agree within 20% of perforated plate AP conversion.

(Not Tech Spec required.)

10.0 ATTACHMENTS ATTACHMENT 1 - SECONDARY CONTAINMENT LEAK RATE SIGNOFF ATTACHMENT 2 - SECONDARY CONTAINHENT CHECK 0FF (BY ELEVATION)

ATTACHMENT 3 - SGTS "A" AIR FLOW VS PERFORATED PLATE AP .

f ATTACHMENT 4 - SGTS "B" AIR FLOW VS PERFORATED PLATE AP 8.7.3 Rev. 29 Page 11 of'23

. ATTACHMENT-1

Sheet 1 of 5 SECONDARY CONTAINMENT LEAK RATE SIGNOFF

[1] Prerequisites (Section 7.0 of the base document)

(a) NHE permission to perform test. Initial V M-(b) Turbine Building H&V System operating, two exhaust and two supply fans in service.

Roof exhausters as required. Initial M.N.

(c) DPI-AA-22 and DPI-AA-32 calibrated. Initial V M /D 0-(d) At least one door at each access closed. Initial P.S.

(e) Standby Gas Treatment System operable. Initial V M-(f) All automatic ventilation system isolation dampers operable or secured in the isolated condition. Initial P.S.

(g) All manometers filled and zerced. Initial F S-(h) Secondary containment checkoff considered and accepted. Initial D.K.

(1) Specific purpose for test performance is: Initial J.H.

[2] Test Performance To verify secondary containment prior to RFO-9 fuel offload per Tech. Spec. 4.7.1.C.

Hind Direction 300 Decrees Hind Velocity 6 mph (115 HPH)

Outside Temperature 35 *F Inside Temperature 74 *F (a) Base Readings Nanometer AP Rx Bldg El. 91' N (1) +.07 "HO2 E (2) +.09 "HO2 8.7.3 Rev. 29 Page 12 of 23

. ATTACHHENT 1

/ Sheet 2 of 5 H (3) +.02 HO 2

S (4) +.16 "HO 2 Average +.085 " H2 O [0"(-0.1 to 0.1") H20]

Elevation 51' Turbine Buildina:

Turb op. floor .15 "HO 2 Condenser Compt. 18 "HO 2 (b) SGTS A Performance Inner Trucklock Door open, Outer Door shut seal >

inflated.

Hanometer Stabilization Time 2.5 min DPI-AA-22 13 " H2 0/ 3800 CFH FI-8126/8127 3100 / 3750 CFM Elevation 91' Rx Blda Manometer:

Igit -

B11e . Corrected N (1) 47 "HO - .07 a HO . .54 "HO 2 2 2 E (2) 41 "HO .09 "HO .50 "HO 2 -

2 2 H (3) .54 "HO - .02 "

HO . .56 "HO2 2 2 S (4) .35 "HO - .16 "

HO . .51 "HO2 2 2 Average corrected manometer AP .53 "HO2 Elevation 51' Turb Blda Manometers:

Turb op Floor 19 "H2O Condenser Compt. .22 "HO 2 l

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8.7.3 Rev. 29 l Page 13 of 23  ;

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ATTACHMENT 1-

-Sheet 3 of 5

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'(c) .SGTS A Performance Inner Trucklock Door shut' seal RQI inflated, Outer Door-open. ,.

DPI-AA-22 1.25 "HO 2 3750 -CFM i

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FI 8126/8127 3100 '/ 3775 CFM Manometer Stabilization Time 4 min Elevation 91' Rx Blda Manometers:

Igit - SAig .- Corrected *

.72 *07 "HO ' ~*79 - "HO N (1) "HO 2 2

2

.70 HO .09 HO ~*79 "HO E (2) 2 2

2

  • 70 "HO .02 "HO .72 "HO H (3) 2 2

2

.45 .16 "HO .61: "HO-S (4) .' H 2O -

2

=

2 Average corrected manometer AP .73 "HO 2 Elevation 51' Turb Bldo Manometers:

6 Turb op Floor 19 "'H 2O Condenser Compt. .22 "HO 2 ,

(d) SGTS B Performance Inner Trucklock Door shut, seal ROI inflated, Outer Door open.

DPI-AA-32 1.35 ..H2O 3850 CFM FI 8126/8127 3275 f 3950 CFM Manometer Stabilization Time 4.25 min l

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.8.7.3 Rev. 29 Page 14.'of 23

. ATTACHMENT 1 Sheet 4 of 5 Elevation 91' Rx Bida Manometers:

1111 -

Blit - Corrected

.66 "HO .07 "HO .73 "HO N (1) 2 2

2

.52 "HO .09 a HO .61 "HO E (2) 2 2

2

.66 "HO .02 "

HO .68 "HO H (3) 2 2

2 S (4) .46 .* H2O -

.16 "

HO - .62 "HO 2 2 Average corrected manometer AP .66 "HO 2 Elevation 51' Turb Bida Manometers:

Turb op Floor .15 "HO 2 Condenser Compt. .18 "HO 2 (e) SGTS B Performance Inner Trucklock Door open, Outer Door shut seal inflated.

DPI-AA-32 1.35 "HO 3850 CFM 2

FI 8126/8127 3250 / 3950 CFM Hanometer Stabilization Time 5.5 min Elevation 91' Rx Blda Manometers:

liit -

Elit - Corrected N (1) .57 "HO .07 "

HO .64 a HO 2 -

2 ,, 2 E (2) .43 "

HO - .09 "

HO - .52 "

HO 2 2 2 H (3) .59 "

HO .02 a HO .61 a HO 2 -

2 2 S (4) .39 a HO .16 "

HO .55 "

HO 2 -

2 2 Average corrected AP 58 "HO 2 Elevation 51' Turb Blda Manometers: ]

Turb op Floor .14 "HO 2 Condenser Compt. 17 "HO 2 i

i 8.7.3 Rev. 29 Page 15 of 23 I

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ATTACHMENT 1 Sheet 5 of 5 (f) System Returned to Normal: (Independent Verification required)

N. Perito Date 4/4/93 Discrepancies-4 L

2 Acceptance Criteria as stated in Section 9.0 of the base document were met.

t' Perito NWE Reviewed By M. Perito NWE Test data forwarded to Compliance Engineer by NWE Date 4/4/93 (g) Reporting l

[Per Technical Specification Table 6.9.1]

Compliance Engineer submitted report to the NRC within approximately lA 90 days.

William Munro 7/12/93 Report Letter # 93-088 Compliance Engineer Date (h) Route to Control Room Annex for filing.

8.7.3 Rev. 29 Page 16 of 23 1

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ATTACHMENT 2 Sheet 1 of 5 SECONDARY CONTAINHENT CHECK-OFF (By Elevation)

The attached check-off sheets provide satisfactory (Sat) or unsatisfactory (Unsat) check-off for various secondary containment penetrations. Satisfactory check-off will indicate the following:

a. For plugs, hatches, and doors: Seals are in place and provide a positive seal around the perimeters of the seal area. '
b. For dampers: Linkage system is clean and free of corrosion. Edge seals are in place and not otherwise damaged. Damper position corresponds to its associated switch position on Panel C7.
c. For drains: Valves are lined up to a minimum 201 full collection tank, tank covers are installed.
d. For water level indication, no low water level alarms are present.

Conditions other than those listed require unsatisfactory check-off and discrepancies noted. Repairs to correct deficiencies shall be initiated.

Inspection of electrical penetrations and masonry for the Reactor Building will be accomplished for all walls annually. Verification of these inspections will be noted as satisfactory if all annual inspections are completed.

El. 3' Reactor Aux. Bay HPCI Floor Blowout Panel & Plugs Sat X Unsat HPCI Escape Hatch Sat X Unsat HPCI Equipment Hatch Sat X Unsat Note Discrepancies:

El. 6' Radwaste ,

Hiscellaneous Tank Drains Sat Unsat X*

Note Discrepancies: * "A" and "B" Miscellaneous Tanks are 28 percent and 2 percent full respectively. "B" Tank is lined up I

per paragraph C.

PASS Area Above Machine Shoo 2 ventilation dampers between Rx Bldg & PASS sample station closed.

PS Veri fied l

8.7.3 Rev. 29 l Page 17 of 23 i i

.- ATTACHMENT 2 Sheet 2 of 5 El. 23' Reactor Buildina X

Trucklock Inner Door Sat Unsat X Unsat Trucklock Outer Door Sat X Unsat Trucklock Dampers Sat X Unsat A0-N-114 Sat X Unsat A0-N-115 Sat X Unsat A0-N-116 Sat X

A0-N-117 Sat Unsat i Personnel Access to Aux. Bay X Unsat Inner Door Sat Sat X Unsat Outer Door Personnel Access to Access Control X Unsat Inner Door Sat Sat X Unsat Outer Door Note Discrepancies:

El. 51' Reactor Buildina Access to HG Set Room Door "A" Inner Sat X Unsat Door "A" Outer Sat X Unsat j Door "B" Inner Sat x Unsat l

Door "B" Outer Sat X Unsat l

l 8.7.3 Rev. 29 Page 18 of 23 l

/ ATTACHMENT 2 Sheet 3 of 5 El. 51' Reactor Buildina (cont'd)

Dampers ,

A0-N-90 Sat. x Unsat , __ \

A0-N-91 Sat X Unsat A0-N-96 Sat x Unsat A0-N-97 Sat x Unsat Note Discrepancies:

El. 74' Reactor Buildina Access to Fan Room 3 X

Inner Door Sat Unsat X

Outer Door Sat Unsat Access to Fan Room 4 '

X Inner Door Sat Unsat X

Outer Door Sat Unsat ,

Access to Fan Room 5 X

Inner Door Sat Unsat X

Outer Door Sat Unsat Dampers X

A0-N-78 Sat Unsat X

A0-N-79 Sat Unsat X

A0-N-80 Sat Unsat X

A0-N-81 Sat Unsat__ l Note Discrepancies:

8.7.3 Rev. 29 Page 19 of 23

ATTACHMENT 2 Sheet 4 of 5 El. 91' Reactor Buildino X Unsat Access to Fan Room 6 Sat X

Inner Door Sat Unsat -

X Outer Door Sat Unsat Dampers A0-N-82 Sat X Unsat AD-N-83 Sat x Unsat L

Note Discrepancies:

El. 117' Reactor Buildina Roof Access (El. 158' 4-1/4")

Inner Door Sat X Unsat Outer Hatch Sat x Unsat__

Note Discrepancies:

8.7.3 Rev. 29 Page 20 of 23

ATTACHMENT 2 Sheet 5 of 5

- El 51' Turbine Buildina Dampers A0-N-92 Sat X Unsat A0-N-93 Sat X Unsat A0-N-94 Sat X Unsat A0-N-95 Sat X Unsat i

Note Discrepancies:

J. H ndy/P. Sweeney Inspected by Date '

Signature hrs issued for repairs N/P as noted Reviewed by K. Kamnschneider for J. Lamoureux Date 4/4/93 Hechanical Systems Engineering Division Approved by M. Perito Date 4/4/93 NWE t

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8.7.3 Rev. 29 Page 21 of 23 l

?.TTACHMENT 11  ;

Sheet-1 of 2 NWE SURVEILLANCE TEST REVIEW This form is to be completed for any surveillance test which is-intended to meet Technical Specification items AND requires NWE review after completion. ' Procedures.

2.1.15, 2.1.16, 2.1 12.1, and 2.1.12.2 are _ exempt from this review. If the surveillance test is complete without discrepancies, this form =is NOT required. l Surveillance Procedure Number 8.7.3 Date 4/4/93

1. Review the surveillance test for exceptions, notes, or discrepancies.

4 If there are ANY exceptions, notes, or discrepancies or the NWE desires additional review, then the STA, SCRE, or NOS shall review the surveillance test in accordance with the criteria of Step 2.

2. Review of Discrepancies:

- The STA (SCRE) or NOS shall document the discrepancy (s) and the review performed to determine acceptance or rejection of the test.

- Cognizant staff engineers or supervisors in the discipline affected may be required to assist in the review.

a. Record the discrepant condition: Use procedure and step number if appropriate.

(1) 9.0 [2] individual baseline readings were equal to O (- 0.1 to ,

+ 0.!) "H2 0. Att. I {21 a. south reading was + 0.16" H20. (2) Misc.

drain tank "B" 2% full. Att. 2 step C Reg. 20% full.  ;

b. Does the condition affect Tech Spec requirements? Yes [x] No [x] ,

4.7.c 0) .(2)

Tech Spec (s) considered Explain basis of decision:

See attached sheet  ;

c. Does the condition prevent restoration of the component, device, or system to operable status as defined in Tech Spec definition 1.0.E? .

Yes [ ] No [x]

Does the condition leave the Surveillance test incomplete with respect to I d.

the component or system tested? Yes [ ] No [x]

Note that Surveillance tests used for postwork testing of specific  :

components may be only partially completed, 1E the subsection of the ,

procedure itself is complete AND the partial test is not used to take '

credit for the entire periodic surveillance test.  ;

1.3.34 Rev. 38 Page 81 of 84

s.

ATTACHMENT 11'

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Sheet.2 of 2 ,

e. Are there any associated system or Plant impacts such as incomplete logic ,

channels or unmonitored trip instruments? Yes [ ] No [x]

Specify associated effects: ,

f. [] If the discrepancy or incomplete steps affect. compliance with MSTP .

commitments, initiate a Problem Report. (PR) to document the portion of the surveillance which must be reperformed and attach the MSTP node printout to the PR. Then annotate 'the master copy of the. Weekly.

Division Schedule located in the Control Room Annex with the completion date and initials in the appropriate spaces.

i PR LC0 MR

[ X] If discrepancies do not impact commitments, the MSTP may be updated. ,

Reviewer comments or concerns:

References used for this review: NED 84-38 7

FS6MC 84-15 l i

Cognizant Engineer / Supervisor R.V. Fairbank (if participant) Signature ,

i This surveillance has been reviewed for discrepancies and it is concluded that the-discrepant condition is: Not Acceptable [] Acceptable [X] i 1

1 Review performed by: K. cracia 4/4/93 i SCRE/STA or NOS Date NWE concurrence with review results M. Perito 4/4/93 __

NWE Date i

This form is to be filed with the Surveillance test reviewed as part of the permanent record.

1.3.34 Rev. 38-Page 82 of 84 i I

1<

1

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<, i J

NWE SURVEILLANCE REVIEW l

2.B. BASIS OF DECISION 8.7.3 Rev. 29 l PERFORMED 4.4.93 l l

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I have reviewed the standby gas treatment system test (Procedure 8.7.3) conducted 4/4/93 with espect to the initial baseline readings and conclude that the test was acceptable.

a NED memo 84-38 dated 1/18/84, identifies the basis for baseline initial conditions j of < 0.1" and > -0.1". (I recall the basis for the baseline limit was-the average of the four readings). Nevertheless, the average baseline prior to this test was 0.085" average. However, one wall was +0.16". Based on plant conditions the baseline is judged to be due to " stack effects" as described in NED mems 84-38. The test results were conservatively influenced by this baseline reading. (i.e., .

starting with a baseline of +0.16 it is that much more difficult for the system to produce an overall negative - 0.25" delta pressure) l Even with this initial positive pressure the test results are clearly acceptable - .

.53" (> .25") after the baseline readings are subtracted. ,

R.V. Fairbank 4/4/93- 3 l

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