ML20149E472
| ML20149E472 | |
| Person / Time | |
|---|---|
| Issue date: | 05/20/1987 |
| From: | King T NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Beckjord E, Morris B, Speis T NRC |
| References | |
| PROJECT-672A NUDOCS 8801130357 | |
| Download: ML20149E472 (6) | |
Text
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MAY 2 01987 p ggf a 7
MEMORANDUM FOR:
Distribution 8
FROM:
Thomas L. King, Acting Chief, ARGIB/DRA/RES
SUBJECT:
MEETING WITH DOE TO REVIEW CHAPTERS 6, 9, 10, 11, 12 AND 13 0F THE MODULAR HTGR PRELIMINARY SAFETY INF0F.ATION DOCUMENT (PSID) r The subject meeting is the fifth of a series of meetings with DOE and its contractors to discuss NRC comments on the conceptual design for the modular HTGR.
The meeting will be held on May 27, 1987 and on May 28, 1987 in Room P-110 and begin at 8:30 a.m. on both days. An agenda is enclosed. The topics I
for each chapter are: Chapter 6, "Buildings and Structures", Chapter 9, l
"Service Systems", Chapter 10, "Steam and Energy Conversion Systems",
Chapter ll, "Operational Radionuclide Control", Chapter 12, "Occupational l
Radiation Protection", Chapter 13. "Conduct of Operation".
Reviewers for these Chapters, together with contractors from ORNL and BNL, should plan to meet in my office at 1:00 p.m. on May 26, 1987 to discuss their planned coments on the subject document.
If you have any questions please contact Pete Williams, the Project Manager (x29613).
/9 Thomas L. Ki g, Acting Chief ARGIB/DRA/RES
Enclosure:
As stated See next page for distribution m
0FC :DRA/ARGIB ARGIB
- DRA/A G,IB
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NAME : W aMs:rr Jr ilson
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DATE :5//9/87
- 5/1 /87
- 5/2,/87
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AGENDA MAY 27, 1987 NRC/ DOE MEETING ON MHTGR PSID CHAPTERS 6, 9, 10, 11, 12 and 13 8:30 am Opening Remarks - NRC, DOE, and Others 8:45 - 9:15 am Overview - DOE, and Others 9:15 - 11:00 am Nuclear Island Building and Structures Chapter 6 - BNI Layout Overview "Safety-Related" Structures-Functions and Requirements Design Description
- Seismic
- Post-Break Venting Additional agenda items or discussions will include the following responses and clarifications: (1) res 12,1987, (2)ponse to General Coment 11 in Morris to Gavigan letter of May how the blow-out panels work and their design bases, (3) is the duct simply concrete or metal lined (PSID page 5.3-3)?
(4) is "controlled venting" of the reactor building considered a "safety-grade" operation? (5) explain the basis for assuming a 30 sq. in. leak in the reactor coolant pressure boundry (PSID page 6.1-6) in setting the vent path and (6) the role of the reactor cavity system in the attenuation factors given i
on PSID page 4.2.5 and discussed in Response 4-8.
11:00 - 12:00 Coments by NRC and Discussion 1:00 - 4:00 pm Nuclear Island Service Systems (Chapter 9)
- Helium Purification System (HPS)
GA
- Reactor Service Subsystem GA
- Fuel Handling and Storage System (FHSS)
GA
- Site Fuel Handling BNI
- Reactor Plant Cooling Water Subsystem (RPCWS)
BNI Spent Fuel Cooling System BNI NI Fire Protection BNI
- NI HVAC BNI The NRC review goals for this and the two following chapters are to assure that (1) all auxiliary and service equipment and procedures that are related to Part 100 guidelines, whether on or off the nuclear island, have bee,n identified, (2) the design is adequate to meet Appendix I and Part 20 requirements, and (3) items identified as non-safety related do not impair by their failure or by improper operation any equipment or procedure important to safety.
In order to expedite the presentations and discussion of these items, the emphasis should be on similarities, improvements or differences of equipment and procedures found acceptable for Fort St. Vrain or LWRs, as appropriate.
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Particular concerns with the agenda items are (1) HPS - lack of principal design criteria, consequences of failures, roles of the LNS and chilled water systems in protecting against failure, (2) Reactor Service Subsystems - while these systems are important to plant operations the NRC does not pl,an to review and comment on the mechanical design of any of these system 9 at the conceptual design stage unless it is judged they significantly impact plant safety.
(S) Fuel Handling and Storage - assurance of prevention of criticality when control rods are removed during(refueling, correctness of orientation and location of freshly installed fuel, 4) RPCWS - failures leading to reactor water ingress or in safety related systems e.g., neutron control assemblies (PSID page 9.1 -85), (5) NI Fire Protection - justification for departure from Appendix R, protection to vital electrical equipment, assurance of operator access to remote shutdown area, hazards from fire off the nuclear island, identification of "backup fire protection services" (PSID 9.1-119), consequence of failures in fire protection systems (including seismic) on meeting 10CFR100 guidelines, interaction of control room fire on plant shutdown and control, description of the carbon dioxide subsystem, test and inspection intervals, independence of fire pump diesel and support systems from plant ac power supply, (6) HVAC - potential as a release pathway from reactor cavity during a LBEs, and (7) Other - safety classification of lighting, comuni-cations, and instrument air systems.
4:00 - 5:00 pm Comments by NRC and Discussion i
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MAY 28, 1987 1
C0"TINUATION OF NRC/ DOE HTGR HEETING, PSID CHAPTERS 10, 11, 12, 13 8:30 - 9:30 am Steam and Energy Conversion Systems (Chapter 10)
- main steam and feedwater systems including "safety-related" NSSS isolation valves 5
" Startup/ Shutdown
- Steam Dump Additional acenda items or discussions should include: (1) possible need for radiation monitors on steam vents and drains, (2) consequences to equipment on nuclear island from turbine missiles, (3) design criteria, functions and safety classification of the service water system, (4) safety classification of the steam and watcr dump system.
9:30 - 10:00 am Comments by NRC and Discussion 10:00 - 11:30 am Operational Radionuclide Control (Chapter 11)
- Radionuclide Design Criteria
- Radwaste Systems
- A00s
- Plant Dose Assessment Presentation and discussions:
For the nuclides given in Table 11.6-1 plus the additional nuclides Te, Ru, Br, Pu, Ba, C-14 data and information should be presented under the followinq column headings in a single table or arrangement of similar tables.
Core Equilibrium - (T.11.1-1) 1 If this is different from total inventory, then add a column "total inventory" and explain the difference.
Core Design Inventory - (T.11.1.2)
Core Maximum Expected Inventory (T.11.1-3)
Plate Out The calculated amount plated out.
Plateout available for liftoff - (T.11.6.1)
If this column is the calculated goal then add also a column of actually anticipated plateout.
Circulating Activity - (T.11.6.1)
If this is the calculated goal then add also a column of actual anticipated circulating activity, l
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c For each column, explain how it was derived and what assumptions were made in the derivation.
In particular, where applicable, explain what role fuel contamination and failed particles play in the derivation.
Discuss the nuclides considered important from the standpoint of comprehensiven,ess.
If you believe any of the nuclides listed above are not important to rtlease estimates and wish to drop them from the table, an explanation should be provided. Also be prepared to discuss if any other nuclides not listed on the table could be important.
In addition, clarification should be provided for:
(1) the significance of A00s and DBEs associated with Radioactive Waste and Fuel Handling and Storage System::, (2) are any fission products retained by failed particles? (if so give referenco and quantify), (3) about half the helium is stated as not circulating-where is it? how does this impact plateout?
(4) how is Fort St. Vrain experience being used to determine plateout activity and to estimate trituim release? and (5) how is the ALARA principal being applied?
11:30 - 12:00 pm Comments by NRC and Discussion 12:00 -
1:00 pm LUNCH 1:00 - 1:30 pm Occupational Radiation Protection (Chapter 12)
Include (1) a description of shielding requirements for the helium purification system, (2) discussion of potential differences in the total exposure estimate from Fort St. Vrain, and (3) will R.G. 1.26 be met for radwaste systems.
1:30 - 2:30 pm conduct of Operations (Chapter 13)
Plant Security d.
Additional agenda items or discussions should include:
(1) review of position on emergency preparedness, (2) administrative controls including potential for and consequences of their failure.
2:30 - 4:0,0 pm Unresolved items Any or all of the subjects listed under Action Item-G-12 in the Morris to Gavigan letter of May 12, 1987 could be discussed at this time.
4:00 pm Adjourn
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e DISTRIBUTION FOR PROJECT 672
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3 ARGIB R/F E. Beckjord T. Speis B. Morris Z. Rosztoczy F
T. King J. N. Wilson P. Williams C. Allen R. Landry J. Flack M. Malloy M. El-Zeftawy R. Baer N. Anderson F. Cherny S. Shaukat R. Kirkwood R. Johnson D. Thatcher' J. Hulman i
J. Glynn L. Soffer J. Read D. Cleary A. Murphy G. Arndt D. Matthews F. Kantor R. Erickson B. Mendelsohn J. Murphy H. VanderMolen E. Chelliah K. Heitner R. Ireland, Reg. IV W. Kennedy F. Coffman L. Beltracchi G. VanTuyle, BNL P. Kroeger, BNL i
S. Ball, ORNL R. Senseney i
Project File 672 PDR L
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