ML20198F088
| ML20198F088 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 12/13/1973 |
| From: | Maccary R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| CON-WNP-0925, CON-WNP-925 NUDOCS 8605280409 | |
| Download: ML20198F088 (5) | |
Text
. - _ _ ___..
D
'~
CEC 131373 Richard C. DeYoung, Assistant Director for Pressurized Water Reactors Directorate of Licensing WASHINGTON PUBLIC POWER SUPPLY SYSTEM - WFPSS NUCLEAR PROJECT NO. 1 (CP), DOCKET No. 50-460 Plant Nemes WPPSS Nuclear Project No.1 Licensing Stage: CP Docket Number 30-460 Responsible Branch and Project Manager: PWR-3; C. W. Rivenbark Requested Completion Date: December 28, 1973 Description of Response Questions - First Round (Q-1)
Review Status: Information Requested Infonnation submitted by the applicant in the PSAR has been reviewed by the Materials Engineering Branch, Directorate of Licensing. Adequate responses to the enclosed request for additional information are required before we can complete our evaluation. In order to maintain the current schedule, the applicant should respond to this request by March 4, 1974.
Ed512;:edby
_IL P. E c:ary R. R. Maccar,, Assistant Director for Engineettag Directorsta o.! Licensing
Enclosure:
Materials Engineering Branch Request for Additional Information (Q-1) cc w/ enc 1:
cc w/o enc 1:
S. H. Hanauer, DRTA A. Ciambusso, L J. M. Hendrie, L W' C' MCM*N' E K. R. Coller, L C. W. Rivenbark, L DISTRIBUTION:
S. S. Pawlicki, L Docket File (50-460)
R. M. Custafson, L L Reading File W. S. Hazelton, L MTEB Files C. Y. Cheng, L P. B. Litton, L 8605280409 731213 PDR ADOCK 05000460 A
o MTEB:L MTEB:L MTEB:L MTEB:L f'-
MTEB:L (E
oma
..w_.f 3.
~.
2 J
. n,
_.._ j<
sv wt
- g,ys'
-,. r, M
sun u nce. 7BLitton/,g1 _c_ygien,
_ysn,+,irnn PMym e r., f a nn _.
c ssPw14 cki RRMaqqg g,
12/6/73 12/ 7 /73 12/7/73 12/,s'/73 124,3 /73 12/f3/73 OAfet.
__.J.=-
-=.-
l Forin ABC.3:e lR.w. 9 53) ABCM 0140 spo c.s se s i.. e. s
..e.
7 e
)
i 1
i i
i l
WASHINGTON PUBLIC POWER SUPPLY SYSTEM LTPSS :.TCLEAR PROJECT NO.1 (CP) i DOCKET NO. 50-460 FIRST REQUEET FCR ADDITIONAL INFORMATION (Q-1)
)
MATERIALS ENGINEERING BRANCH, L I
REACTOR I
Reactor Vessel [nternals
}
Provide a list of materials, and their specifications, used for each j
l major component of the reactor internals. Specifically, state if the following secels having yield strengths greater than 90,000 psi are used: cold-worked austenitic stainless steels, precipitation hardening b
stainless steels, or hardenable martensitic stainless steels.
If any I
such steels are employed, provide assurance that they will be compatible i
with the reactor coolant.
1 3
l l
}
l e
[
l l
l
-,.--w-m-
3-
-..-.,v r.,p
REACTOR CCOLUiT SYSTEM A"D C0m?ECTED SYSTEM $
Fracture Touchness Provide copies of the Topical Report BA*a*-10046, " Fracture Tcughness Requirements " for our review and evaluation.
Indicate that the fracture toughness requirements, operating limitations, t
and reactor veesel materials surveillance program will comply with Appendices G and H of 10 CFI 50, as published in the Federal Register, July 17, 1973.
i Fump r!yuheel i
i State your intention that the pump flywheel will be designed so that the combined primary otresses at the design overspeed, due to centrifugal forces and the interference fit, will not exceed the limit recommended e
in the Regulatory Guide 1.14. " Reactor Coolant Pump Flywheel Integrity,"
issued October 27, 1971. Also, the inservice inspection program (Table 5.2-8) for each flywheel should be modified to include a surface 4
examination of all exposed surfaces at approximately 10-year intervals
]
during the plant shutdown to ensure safe operation.
RCPB lenkage Detection Provide information to indicate that the leakage detection systems will be capable of performing taeir functions following seismic events not requiring plant shutdown and that the airborne particulate radioactivity
~
monitoring system will remain functional following an SSE seismic event.
7 F
b I
1
I f
f I
i 3 -
Indicate that the leakage detection methods will be sufficiently sensitive to give results comparable to those obtained by conformance with Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leskage Detection Systems,"
issued May 1973. Submit a table of the leakage detection methods and include the sensitivity (gpm) and response time of each system.
In addition, the total leakage rate limit of 30 gpm is unacceptable. The Regulatory position is that each leakage detection system should be capable of detecting an unidentified leakage of one gpm in one hour or less and the acceptable total leakage rate limit is 10 gpm and that for unidentified sources is 1 gpm.
i N
,.. _ _ _ _ _ - ~ -. _
_= _.. _ _ _. _ _ _ _ _
O l
1 i
i d
1 7
4
_4_
i ENGINEERED SAFETY FEATURES Inservice Inspection Program Provide sufficient Information about your proposed ESF inservice inspection program to indicate that the program for Class 3 components will provide a degree of assurance of system integrity comparable to the program recommended in Regulatory Guide 1.51, " Inservice Inspection of ASME Code Class 2 and 3 Nuclear Power Plant Components," issued May 1973.
i I
3 l
)
i i
i l
a i
I l
i
,.-__.,-,___,_.,,_.______-m__._..__
-