ML091190090

From kanterella
Revision as of 06:40, 14 November 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
E-mail from J. Richmond of USNRC to J. Kulp and S. Pindale of USNRC, Regarding Drawing Attached for Oc Outage Inspection Plan
ML091190090
Person / Time
Site: Oyster Creek
Issue date: 10/21/2008
From: Richmond J
Engineering Region 1 Branch 1
To: Jeffrey Kulp, Stephen Pindale
NRC/RGN-I/DRP/PB6, Engineering Region 1 Branch 2
References
FOIA/PA-2009-0070
Download: ML091190090 (15)


Text

John Richmond From: John Richmond -

Sent: Tuesday, October 21, 2008 1:30 PM To: Jeffrey Kulp; Stephen Pindale Cc: Ronald Bellamy; Scott Barber; Marc Ferdas; Michael Modes; Timothy OHara; Richard Conte

Subject:

Drawing attached for RE: OC Outage Inspection Plan Attachments: OC View from inside Drywell.jpg; OC Drywell Elevation & Regions.bmp; OC Drywell Key Plan.jpg; OC Drywell Liner Thicknesses.jpg; OC Drywell Support Structure.jpg; OC Drywell Trench, Bay-5.jpg; OC Drywell Trench, Bay-1 7.jpg; OC Drywell X-section.jpg; OC Rx Cavity Detail.jpg; OC Rx Cavity Trough Drain Detail.jpg; OC Sandbed Detail-i .jpg; OC Sandbed Detail-2.jpg; OC Sandbed, Trench, & Sump.jpg All of the attached drawings came from Public Records (ACRS & ASLB presentations).

These drawings may be helpful when discussing various drywell issues.

From: John Richmond Sent: Monday, September 29, 2008 2:04 PM To: Marc Ferdas; Jeffrey Kulp Cc: Stephen Pindale; Ronald Bellamy; Scott Barber

Subject:

OC Outage Inspection Plan Marc/Jeff, can you include the following License Renewal items in the Resident Outage Inspection Plan?

1. As soon as reasonably achievable after the Drywell is opened, verify condition of both D/W Trenches (dry, wet, water stains, etc.). Pictures are optional, but always nice.
2. Within about 1-shift after the cavity is flooded up, verify the reactor cavity trough drain leakage rate (we do expect some leakage). After the initial check, continue to check it, about once per day, for a day or two, to see if the leakage rate changes. During 1R21 (2006), the continuous leakage was identified at about 1 gpm, while the cavity was flooded.
3. Within about 1-shift after the cavity is flooded up, verify the 5 D/W sandbed drains, drain collection bottles.

No water or leakage is expected.

4. AmerGen is to apply a strippable coating, as a sealant, in the reactor cavity prior to flood up, to limit cavity seal leakage that could end up in the sandbed area. While you are welcome to observe or inspect this item, my team will verify this item, by a records review, after we arrive on-site.
5. During this outage, AmerGen is suppose to replace some ESW pipe. I understand the pipe has already been laid/installed, and is waiting to be "tied-in" during the outage. Did the Residents observe any portion of the new EtSW pipe installation?

Thanks John Richmond

Received: from R1CLSTRO1 .nrc.gov ([148.184.99.7]) by R1 MS01 .nrc.gov

([148.184.99.10]) with mapi; Tue, 21 Oct 2008 13:29:47 -0400 Content-Type: application/ms-tnef; name="winmail.dat" Content-Transfer-Encoding: binary From: John Richmond <John. Richmond@nrc.gov>

To: Jeffrey Kulp <Jeffrey.Kulp@nrc.gov>, Stephen Pindale

<Stephen. Pindale@nrc.gov>

CC: Ronald Bellamy <Ronald.Bellamy@nrc.gov>, Scott Barber

<Scott.Barber@nrc.gov>, Marc Ferdas <Marc.Ferdas@nrc.gov>, Michael Modes

<Michael.Modes@nrc.gov>, Timothy OHara <Timothy.OHara@nrc.gov>, Richard Conte

<Richard. Conte@nrc.gov>

Date: Tue, 21 Oct 2008 13:29:44 -0400

Subject:

Drawing attached for RE: OC Outage Inspection Plan Thread-Topic: Drawing attached for RE: OC Outage Inspection Plan Thread-Index: AckiXbveQcOAazRyQ8uNcVdUr4+eVgRRFfBQ Message-ID: <2856BC46F6A308418F033D973BBOEE72AA2A4DC877@R1CLSTRO1 .nrc.gov>

References:

<2856BC46F6A308418F033D973BBOEE72969755C4FC@R1CLSTRO1 .nrc.gov>

In-Reply-To: <2856BC46F6A308418F033D973BBOEE72969755C4FC@R1CLSTRO1 .nrc.gov>

Accept-Language: en-US Content-Language: en-US X-MS-Has-Attach: yes X-MS-Exchange-Organization-SCL: -1 X-MS-TNEF-Correlator:

<2856BC46F6A308418F033D973BBOEE72AA2A4DC877@R1 CLSTR01.nrc.gov>

MIME-Version: 1.0

VIEW FROM INSIDE DRYWELL UPPER CURB - EL. 12'.3" TOP OF SANDBED

. _jL Al A1.

0 El E 8i ,7 4 LOWER CURB

.

A6 A A A 4

  • 7 *7 A A 11'-0"

<1 A DRYWELL FLOOR - EL., 10'-3"

REACTOR BUILDING, DRYWELL SUPPORT STRUCTURE

-I--

I CONTAINMENT SHELL SANDBED REGION---\ EL. 23'-6" GRADE EL. 23'-6" J

&REACTOR VESSEL CURB DRYWELL FLOOR

~/

EL. 10'-3"

-EL. 5'-D" LIMIT OF TORUS - MEMBRANE L

1" . L-EL. 4'-6""

WATERPROOFING N'

,1 MEMBRANE WATERPROOFING (TYP ALL AROUND)

. .- PEDESTAL - WATER STOP (TYP)

TYGON ALL AROUND)

TUBING

¸---.--'i -'

,.- I P Uh MAI 4>

  • EL. _l9-j A-A 5 GALLON io,-o- *POLY BOTTLE 1 4r44

-CONCRETE MAT I *.* I '~4Z A:'

-. A .' A *~' -A ~

L 43'-6" EMEMBRANE WATERPROOFING LEVELING SLAB

REACTOR CAVITY STAINLESS STEEL LINER----

CONCRETE

  • SEE DETAIL "B'L----\

REACTOR VESSEL DRYWELL AND REACTOR CAVITY SECTION DETAIL "A"

Head Iso Elevation 94'-9" View Cy

.*

00 Azimut

.900 AzimL Elevation 71'-10" 2700 Azin Elevation 65'-4" "L.- Knuc 50'-11 ' Uppe

--- Mid(

tion 37'43 Per!

ition 27'-6" & Equ

.tion 23'-6" H Lower CVer (10

\

4

.4 TOP OF SANDBED EL. 12'-3" & UPPER CURB LOWER CURB EL. 11-DRYVA WALL

  • t A

FLOOR EL. 10'-3" 44 4 4, 4.

4 . 4 4

-. .4

~* 4

-. A REG ION .4 4.

4

4 4 4'.

.4 ' 4"

"*,o EL. 8'-99 EXCAVATION 4 4

4'

.4 4.

4/ "

,t,

  • 4.44 .4 A 4 A

.4 A

BAY 5 -TRENCH

.4 4 4.

4 44

.4

.4' 4 4 44 A ~.

4..4

.4. 4 4'

4.

.4_ 44 ~ .

4.

.4 :4 4

4 4

4 4.. .4, 4

. 4 4. 4 4 4

A 4 .

  1. , 4 4a

DRYWELL TO REACTOR CAVITY SEAL DETAIL DETAIL 'B' OBSERVEDDAMAGE-AT LIP OF TROUGH CORRECTED IN 1988

EL, 87'-6" (12)

F EL. 51f-.1O (8.9)/

TRENH .. EL. 60'-1 (100)

NOTE:

NUMBERS IN PARENTHESES, REFER TO.THE ATTACHEDGRAPH IDENTIFCATION NUMBERS KEY PLAN

TOD OF SANDBED EL. 12"--3" & UPPER CURB LOWER CURB EL. 11'-0" DRYWELL WALL FLOOR EL. 10'-Y" 4 4 .4

4-

>4 4 4, '

h,' 4. 4 4.. 4 A

.4 4

SANDBED

'4 REGION EL. 9'-3 .4

.4 3/4 4> 4 4 - .4 4 '.4' A 4 44 4.

'0.

4. .4 47 A' ~ 4 .

4, .4 4 '4 4 4 4 4- 4. 4 44

  • AY 17 - RNC' 44

.4' 44 A

4' 4.4. ~

4' 4 44' A ,,

"'.4

4. 4 4 4 4,. 4

.,A A ~ 4.

'4 . 4

,4'4 , .4

.4' 4 '. 44, 4 4 '. .4 4 4.

LOWER DRYWELL/SANDBED REGION NOTE:

LEAKAGE PATH FROM OUTER DRYWELL TO OUTER DETAIL C SANDBED SHELL /

SANDBED REGION 15">

.BOTTOM F SANDBED

° -l E ,

DRYWE.LL

/_ N EL. 87'-5"

'7,. UT READINGS IN THIS AREA EL. 51'-10" ___EL. 60'- 10"

,, UT READINGS IN THIS AREA EL. 50'-2" UT READINGS IN THESE AREAS EL. _12'-,3" EL. 8'- 11 TOP OF SANDBED BOTTOM OF SANDBED SUPPORT SKIRT -

(SEE DETAIL 1) 1.154" UT READINGS IN THIS AREA-

DETAIL WA" DETAIL "B' DETAIL 'C'

i 6

SURE PLATE SAND BED AREA 0.770" THK EL. 12'-3"-

TOP OF SANDBED & UPPER CURB RADIUS = 19'-5 7/16" 1.154" THK PLATE EL. 8'-1 1" STABILIZING RING - EL. 8'--1 "

EL. 6.'-10 5/16'----

4' DRAIN PIPE (5 PLACES) 0.676" THK PLATE

( DRYWELL BOTTOM I

-EL. 2'-3" 1/2" PLATE

-- -EL. (-)0'-1" SECTIONAL VIEW OF SAND BED AREA AT VENT PIPE

LOWER DRYWELL-SANDBED, TRENCH & SUMP ELEVATION LOOKING WEST