ML20210T278
| ML20210T278 | |
| Person / Time | |
|---|---|
| Site: | Satsop |
| Issue date: | 09/24/1974 |
| From: | Stello V US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| CON-WNP-1344 NUDOCS 8605300011 | |
| Download: ML20210T278 (3) | |
Text
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l SEP h u Docket Nos.: 50-508/509 Richard C. DeYoung, Jr., Assistant Director for LWR's, Group 1. L FIRST ROUND QUESTI0t6 - WASHINGTON NUCLEAR PROJECT NO. 3 & 5 Plant Name: Washington Fuclear Project. Units 3 & 5 Licensing Stage: CP Docket tios.: 50-533-509 Responsibic Dranch and Project Leader: LWR 1-3, P. O'Reilly Requested Cor71etion Date: October 11, 1974 Applicant's Response Date Necessary for Completion of Next Action Planned on Project: November 29, 1974 Review Status: Awaiting Information Adequate responses to the enclosed list of questions prepared by the Reactor Systems Dranch are required t* fore we can complete our review of the subject application. This request concerns compliance by the applicant with the Codes and Standards Rule. Sectias 50.55a of 10 CFR Part 50, Systen Quality Group Classifications and Seismic Classifications of fluid systems important to safety.
Nrf oal si, cert by Nictor stry Victor Stello, Jr., Assistant Director for Reactor Safety Directorate of Licensing
Enclosure:
Question List
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211-1 211.0 REACTOR SYSTEMS BRANCH 211.1 In Section 3.2.1, you state that excluded frog Seismic Category (3.2.1)
I classification will be Safety Class 3 components which when assumed to simultaneously fail following an SSE will result in offsite exposures !.alow 500 mrem whole body. To facilitate our review, clearly indicate on the piping and instrument diagrams the Safety Class 3 components which are 'not Seismic Category I.
211.2 In Table 3.2-1, indicate the classifications of the piping and (3.2) valves of the containment vacuum relief system.
211.3 In Table 3.2-1, the fuel handling area ventilation system is (3.2) listed as non Seismic Category I.
However, the isolation dampers for this system are safety related and are classified Seismic Category I according to Section 9.4.2.4.3.
Revise Table 3.2-1 to indicate the classification of these isolation dampers.
211.4 Failure of any of the diesel generator auxiliary systems will (3.2) prevent the diesel generator from perfonning its safety function.
Therefore, each of these auxiliary systems, including lube oil, air 4
starting, cooling water and fuel oil, should be designed and con-structed to h fety Class 3', Quality Group C, and Seismic Category
'I requirements to the maximum extent possible. Excluded from the ASME Section !!!,7' Class 3 requirements of Quality Group C is any component either not available as ASME Section III or more suitable for the intended service than a similar component constructed to ASME Section III req 01rements. Table 3.2-1 should be revised to include these systems.
211.5 Note 2 of Table 3.2-1 states that the cooling water and/or seal (3.2) water systems for the reactor coolant pumps are not necessarily Safety Class 2 or Seismic Category I.
The safety classifications indicated on the piping and instrument diagrrms for the reactor coolant pump seal system are acceptable. However, if you intend to classify the cooling lines to the RCP seal coolers as non Seismic Category I, provide a detailed analysis of the consequences
-of the failure of these lines. The analysis should include calcu-lations which show that there is no possibility of RCP seizure as a result of the loss of cooling water to the seal coolers.
211.6 Note "C" of Table 3.2-2 implies that pumps classified A, 8 or C (3.2) will comply with ASME Section I!! requirements only to the extent of well thickness and cover bolting size. Revise this note to clarify that Class A, B or C pumps will be designed, constructed and tested in complete accordance with ASME Section III require-ments.
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- 6-211-2 211.7 Several of the CESSAR piping and instrumentation diagrams included (3.2) in Section 3.2 contain minor errors in the piping classification details which have been corrected in the CESSAR Amendment 6, of August 19, 1974. State your intentions in regard to the use of the more recent CESSAR P&ID's.
211.8 In Figure 3.2-1, the line from the reactor vessel to the reactor
'(3.2) drain tank is color coded Safety Class 1 (red) but is labeled SC-4(CESSARdesignation). Furthermore Amendment 6 of CESSAR indicates this line to be Safety Class 2 out to and including the automatic isolation valve. The latter classification is considered acceptable. Resolve this inconsistency and revise Figure 3.2-1 accordingly.
211.9 InFigure3.2-4,theNNSclasslficationofthelevelinstru-(3.2) mentation is not considered acceptable. These lines should be Safety Class 2.
211.10 In Figure 3.2-13, the isolation valves in the non essential (3.2) header to the waste gas compressors, etc. are color coded correctly but the classification change boundary is shown incorrectly. Revise Figure 3.2-13 to include the isolation valves in the SC-3 portion of the system.
211.11 In Figure 3.2-15, the main steam sample lines should be (3.2) classified Safety Class 2 out to and including the first normally closed valves or valve capable of automatic closure. Revise this Figure accordingly.
211.12 Revise Figures 9.4-1, 9.4-2, and 9.4 3 to indicate the safety (9.4) classification of each of the system components.
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SEP 1 7 SN Docket Noe.
STN 50-50R i
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l Olan D. Parr Chief, Light Water Reacters Project Breach 1-3, L FORTRCOMING MRETING WITH WASHINGTON PUBLIC POWER SUPPLY SYSTEM REGARDINC WFPSS NUCLEAR PROJECTS NO. 3 AND NO. 5 Date:
September 20, 1974 Time I, Location:
8:30 a.m. - Boom P-114 Bethesda, MD 1:00 p.m. - Room P-126 Bethesda,19
Purpose:
To discuss questions regarding quality assurance, mechanical engineering, materials engineering, effluent treatment systems, containment systems, and auxiliary power and comersion systems (see attached agenda).
Participants:
WASHIMCTON PUBLIC POWER gUFFLY SYSTEM (G. Sorensen, R. Dellums, R. Johnson)
ERASC0 (R. Vickers)
COMEUSTION ENGINEERING (E. Guenther)
AEC - STAFF (P. D. O'Reilly, J. Costello*, P. Chen*,
P. Cherney *, E. Brooke*, C. Liang*,
M. Boletsky*, P. Stoddart*)
Original Signed Bf O. D. Parr strick D. O'Reilly Light Utter Rosetors Project Branch 1-3 Directorate of Licensing
- Denotes part time attendance as required Attachments
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AGENDA I.
Quality Assurance 1.
QA Organization 2.
QA During Design and Construction II.
Effluent Treatment Systems 1.
Source Terma 2.
Liquid Weste Systems 1
Gaseous Waste Systems 4
Solid Waste System 5.
Process and Effluent Radiological Monitoring System III. Mechanical Engineering 1.
Protection Against Dynamic Effects Associated with the Postulated Rupture of Piping 2.
Mechanical Systems and Components 3.
Preoperational Vibration of Reactor Internals 4.
Pumps and Valves 5.
Seismic Design of Category I Instrumentation and Electrical Equipment 6.
Mechanical Design of Reactor Vessel Internals 7.
Mechanical Design of Reactivity Control Systems 8.
Design of Reactor Coolant Pressure Boundary Components IV.
Containment Systems 1.
Sub-compartment Pressure Analysis 2.
Combustible Gas Control V.
Auxiliary Power and Control Systems 1.
Fuel Storage and Handling 2.
Water Systems
i i 3.
Process Auxiliaries 4.
Air Conditioning, Heating, Cooling, and Ventilation Systems 5.
Other Auxiliary Systems 6.
Steam and Power Conversion System 7.
Turbine Generator 8.
Main Steam Supply System 9.
Other Features of Steam and Power Conversion System
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Distribution:
Docket Fihe#
F. Schroeder AEC PDR H. Denton Local PDR R. Maccary LWR l-3 R3ading V. Stello LWR l-3 File R. Tedesco L Reading V. Benaroya E. G. Case C. Long A. Giambusso J. Kastner R. 5. Boyd G. Lainas R. C. DeYoung D. Ross R. W. Klecker T. Ippolito D. Eisenhut S. Pawlicki R. Denise J. Knight K. Goller L. Shao I
D. Muller B. Grimes D. Skovholt W. Gammill V. Moore R. Ballard W. Butler P. Fine D. Vassallo T. Novak K. Kniel M. Spangler A. Schwencer A. Kenneke J. Stolz R. F. Fraley, ACRS (16)
R. A. Clark S. Varga R. Ireland EP Project Manager -
J. Norris R. Purple OGC D. Ziemann R0(3)
P. Collins RS(3)
R. Vollmer V. Wilson W. Houston Receptionist, Bethesda G. Knighton P. O'Reilly G. Dicker I. Sihweil D. J. Youngblood C. Stepp W. H. Regan, Jr.
D. Bernreuter C. Lear E. Hawkins T. Johnson F. Kantor T. Murphy J. Costello P. Chen F. Cherney E. Brooks C. Liang M. Bolotsky P. Stoddart w
SEF 111974 Docket lbs. S 50-508 arul -
! 50-509 Olan D. Parr, Otlef, Light Mater Reactors Project Branch 1-3, L 10RTitXNIE WPPSS MJCLEAR FIKUBCTS.W. 3 NO 10. 5 STE' VISIT Am Pe! TIE Wr!!! MA!HI'GIUh PUNLIC POMR SUPPLY SETBt Time and Date:
8:30 A. M. - Septem6er 16-17,1974 Location:
MTSS Nclant Projects No. 3 and W. 5 site Satsop, Washington
Purpose:
Tour site and disass certain questions related to seismology, meteorology, hydrology, rajlological i
assessment, and accident analysis (see attached agenda).
Participants:
WASHIICION PUBLIC POER SJPPLY SYSTBI (G. Sorenson, D. Tillson, D. Whitford, R. Nicklas, K. Wise)
+
EBASCD (R. Vickers, A. Wern, J. Mauro, T. Donnaher, J. Kinney)
WOODWARD - WNDGRTR (A. Patwardhan)
USAEC - RB(UIA10mf STAFF (C. Stepp, D. Bernreuter, E. Iluukins, T. Johnson, F. Kanter, T. Murphy, R. Earnasiewicz, P. O'Reilly)
Original Signed by Patrick D. O'Relily Patrick D. O'Reilly Light Mster Reactors Project Branch 1-3 Directorate of Licensing
Enclosure:
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T M o-b!EETING AGINDA 1.
b!cteorology A.
Regional Climatology B.
Local hieteorology C.
Onsite h!eteorological Program D.
Short Tcrn (Accident) Diffusion Estimates E.
Long Tem (Routine) Diffusion Estimates 2.
Ilydrology A.
Floods B.
151F on Streans and Rivers C.
Potential,D.in Failures (Seisnically Induced)
D.
Probabic :.taxinta Surge and Seiche Flooding E.
Probable \\1axir.an Tsunani Flooding, F.
Ice 1:loodin.:
G.
Cooling hater Canals and Reservoir 11.
Channel Diversions 1.
Floodin;' Protection Requirenents J.
Low Uater Censiderations K.
Environr.cntal Acceptance of Effluents L.
Ground Kater 3.
Seismology A.
Vibratory Ground ?!otion B.
Surface Faulting C.
Stability of Subsurface !!aterials D.
Geophysical Investigations E.
Remote Sensing F.
Local Fault Investiration G.
blicro-Earthquake Survey 4.
Accident Analysis A.
Geography and De:.iography 11.
Population and Fopulation Distribution C.
Uses of Aljacent Lands and Waters D.
Nearby Industrial Transportation, and h!ilitary Facilities E.
Evaluations F.
liabitability Systems G.
Radioactivity Gas Release 5.
Radiological Assessment A.
Shielding B.
Ventilation C.
Ilealth Physics Program D.
Offsite Itadiological h!anitoring Program
I i
Distribution:
Docket filev' F. Schroeder AEC PDR H. Denton Local POR R. Maccary LWR 1-3 Reading V. Stello LWR l-3 file R. Tedesco L Reading V. Benaroya E. G. Case C. Long A. Giambusso J. Kastner R. S. Boyd G. Lainas R. C. DeYoung D. Ross R. W. Klecker T. Ippolito D. Eisenhut
- 5. Pawlicki R. Denise J. Knight K. Goller L. Shao D. Muller B. Grimes D. Skovholt W. Gammill V. Moore R. Ballard W. Butler P. Fine D. Vassallo T. fiovak K. Kniel M. Spangler A. Schwencer A. Kenneke J. Stolz R. F. Fraley, ACRS (16)
R. A. Clark S. Varga R. Ireland EP Project Manager - J. Norris R. Purple OGC D. Ziemann R0 (3)
P. Collins RS (3)
R. Vollmer V. Wilson W. Houston Receptionist, Bethesda G. Knighton P. O'Reilly G. Dicker G. J. Youngblood W. H. Regan, Jr.
- - -