ML19224D294
| ML19224D294 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/13/1979 |
| From: | Miraglia F Office of Nuclear Reactor Regulation |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7907110306 | |
| Download: ML19224D294 (6) | |
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' 3T NUCLEAR REGULATORY CCMMISSICN 4
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W ASHINGTO N, 0. C. 205 55
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,s, v j NOTE TO:
V. Stello, Jr., Director, TMI Cperations FRCM:
F. J. Miraglia, Jr., Coordinator, Team 3 The attached report on penetration availability was prepared by IEC3 staff and is provided for your informaticn.
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F. J.C,d P, Jr.
.k Coordinator Team B
Attachment:
As Stated cc: see attached distribution list e
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PE?iETRATICli AVAILABILITI t'.
" " PACT: This report presents, in abreviated form, a summary of the Staff's efforts in evaluating the ability to acnitor the Three Mile Island Unit 2 reactor pressure and level using instruments outside of the containment.
ItiTRODUCTICil: The following penetrations were identified by Bill Millstead as being suitable for making pressure measurements during natural ircul a tion.
(1) PR 538 (2) R 541 (3) R 546 (4) R 591 (5) R 592
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n DISCL s5ICti:
It was recognized that scme of these penetrations are separated M
from the primary sys'em by check valves which swing in tha " wrong" direction, but Chuck Graves of the RSS has stated that pressure measurements can be made (once the valve is 1 ~'ted off of its seat) as long as no flow occurs in the out of containment direction.
FIlIDI?tGS:
1.
The following penetrations / valve strings are available for measuring pressure:
PEffETRATICil VALVES (inboard cut)
(a) R 538 RC-V11' Pressuricer CA-V1 steam space J
RC-V122 Pressurizer CA-V3 water space RC-V123 RC-P-1A CA-V6 Suction C
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i (b) R 541 MU-V1A or MU-Vl B RC-P-1A i
and MU-VZA or MU-V2B Suction (both A or both B)
(c) R 591 cr R592 RC Pump discharge Isolated by inbna-1 check valve little or no flow will be tolerated (d) R 546 C;-V2A or B Core Flood tank Vents WDG-V2 2.
The foll-g combinations or penetrations and valve strings are presented in lighest to icwest point of ccnnection to the
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primary system.
(a) k 546 CP V3A & WCG-V2 CF V3B & WDG-V2 (b) R 538 RC-Vil7 i CA-V1
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(c) R 538 RC-V123 & CA-V6 R 541 MU-VlA & MU-V2A MU-VlB & MU-V23 R 591 MU-V402C R 592 MU-V402D (d) R 538 RC-V122 & CA-V3 The following valves are not pcwered by onsite sources, 3.
RC-Vil 7, RC-V122, RC-V123, CF-V3A, CF-V38, CF-VZA, and CF-V23.
4.
Of the valves which are powered by onsite sources, the folicwing -
penetrations are associated:
(a) R 538 Division 2(CA-V1, V3, V5)
(b) R 541 Beth Divisions (MU-V13 1 28)*
Division 1 (MU-Vl A & 2A)*
- including interlocks (c) R 546 Division 2 (UDG-V2)
(d) R 591 1592 No electrical valves inboard y,
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3 The location of the sample points are in TMI Unit 1 l Tcwer and 5
N; clear Sampling Rccm in the TMI Unit 1 Contro the Unit 2 Sample Hood.
t known.
The elevations of the pipe runs and penetrations are no 6.
h qualifi-The following vah'es have been verified as meeting t e i
2S6'E 7.
3.11.2 (60 ps g, cations stated in FSAR Section
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These are Limitorque valve Rad).
100". RH, and 2.8 x 10 actuators RC-Vil7 CA-V1 RC-V122 RC-V123 CA-V 6 f
tion The folicwing documents were used to obtain the in orm 8.
above:
REFERENCE PENETRATION DWG 2034, 2031 (a) R 538 FSAR Tables 6.2-15 9.3-2 FSAR Figures of 8.3 and 9.3-2 DWG 2024, 2029
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(b) R 541 FSAR Table 6.2-15 FSAR Section 8.3 OWG 2028, 2024, 203?
(c) R 546 CWG 2024 (d) R 591 & 592
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Conclusions:==
Based on the information which is presently available:
riast of the motor operated valves of interest are Limitorque valves i.
and are qualified beyond 2.8 x 10 Rad.
Therefore, radiation induced damage need not be considered.
2.
It is not prudent to use any of the available penetration points to attempt to infer any sort of level information t,<
- ifferantial pressure.
RECCMMENDATIONS:
Based on the available data and the conclusions which cre drawn therefrom the staff recommends:
1.
That the available penetrations not be used for differential pressure measuremer:ts until more is known about the actual routing (and therefore elevations),of the affected piping.
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2.
That, should recommendations i be disrecarded, the following penetration /
valve pairs be used as (a) First Choice:
Reference leg R 546 (CFV3A or CFV33 and WDG-V2)
Measureo leg R538 (RCV122&CA-V3)
(b) Second Choice R 546 (CFV3A or CFV3B and WDG-V2)
Measured leg R 538 (RC-V123&CA-V6)
(c) Third Choice Reference leg R 538 (RC-Vil7 & CA-V1)
Measured leg R 541 (MU-VlA & MU-V2A) or (MU-Bl3 & MU-V23)
(!n the event that valves CF/WDA are used it will be necessary to charge the liner by filling the core flocding tanks through the N2 supply or the tank cross connect lines)
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i relative heights of the penetrat on h
(It will also be necessary to determine t ei h is actually being (It could and used to determine the level wh c VI if up being negative) flow established via RCV177 & CA-(The pressurizer must be flooded withll result in an atmospheric r alternative 3 is used) This wie measurement is R 528 via RCV1 22 &
The best penetration of system pressur his time.
3.
in Re. alt 3 above should be opened at t CA-V3 i
Ali valves which are listed) should be provided for the follow ng 4.
Isometric drawings (with dimensions
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from the steam space to val <a piping runs:
Pressurizer steam space sacole line
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(a) i rizer water space to penetrat on CA-V208.
Pressurizer water space from the pressu (b) letdown tap to valve CA-V6.
R 528.
coolant pump RC-P-1A suction to valve MU-V376.
Reactor (c)
Reactor Coolant Pcmp RC-P-1A suction 6C.
(d)
Discharge of RC-P-2A to valve MU-V1 160.
(e)
Discharge of RC-P-1 A to valve PU-V ATICH R 546.
(f)
Core Flood Tanks lA and 13 to PENETR (except et the pressurizer) should be (g)
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No external pressure measurement t pump is operating.
6.
l attempted while a reactor coo an
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