ML20039H202
Text
b 3
\\
Distribution:
Docket Files F. Williams NRC POR
- 0. Par Local POR T. Co LWR #3 File M. Rushbrook D. Vassallo OELD (3)
BCC: J8uchanan Occket No. ST't 50-561 MAY 01 TAbernathy ACRS (16)
Babcock & Wilcox Company ATTM: Mr. James H. Taylor Manager of Licensing Nuclear Power Generation Division P. O. Box 1260 Lynchburg, Virginia 24505 Gentlemen:
SUBJECT:
OUTSTMUING ISSUE REGARDING CAPABILITY FOR COLD SHUTDOWN OF BSAR-205 DESIGN In our Report to the Advisory Coswittee on Reactor Safeguards in
_._ July _1__977,.we_ stated that we were considering, on a generic basis, whether the capability should be provided for transferring heat from the reactor to the environment, during the transition from normal reactor operating conditions to cold shutdown, using coly safety grade systens, and assuming (1) only offsite or onsite pcwer is available and (2) the most limiting single failure has occurred. 'Je also stated that we might require the BSAR-205 design and tne designs of the balance-of-plant portions of applications referencing BSAR-205 to be modified to provide such cold shutdown capability.
In the wriod following our Report to the ACRS, a final decision on this matter was taken by our Regulatory Requirenents Review Comittee, in a memorandum from E. G. Case, Comittee Chairman, to L. Y. Gossick, Executive Director for Ooerations, dated February 16,1978. This decision established that specific technical requirements shall be locarporated in overall plant designs for which construction pemit or Preliminary Design Approval applications were docksted before January 1,1978, and for which operating license issuance is expected after January 1,1979. This includes, among others, the BSAR-20S Preliminary Design Approval (PDA) application and the ERIE I and 2 construction pemit application by the Ohio Edison Company.
8201190714 810403 PDR FOIA MADDEN 80-515 PDR j...
eaet e=
NRC PORM SIS (MG) NRCM 0240 t u. a. eevaa.emse **wuse emeen 'ete - see ene a
F
)
(
M M 0 1 1978 Babcock & Wilcox Company l Cur specific technical requirenents for plants referencing the BSAR-205 design were transmitted to Mr. J. Lauer of your staff by telecopy on April 10,1978. These requi nments are included in the Enclosure.
In two " working level" telephone conferences on April 21 and April 27, our respective staffs have discussed the degree to which the SSAR-205 Preliminary Safety Analysis report documents compliance with, or provides infomation necessary for referencing applicant compliance with, our seven requirenents for cold shutdown capability.
We indicated to your staff that your femal commit:: lent to our requirenents would satisfactorily complet. your response to the cold shutdown issue at the PDA stage of review. However, your staff noted that the alternatives to safety grade equipment, as stated in items 2. 3, and 4 of our reouire-i
-)ents, were at least partly within a referencing applicant's design scope.
Further, your staff stated that it would be difficult for B&W to comit to the requirenents as written because of the non-quantitative nature of l
the allowed alternatives, e.g., "...or show that manual actions inside or j
outside containr:ent or return to hot standby... provides an acceptable i
alternative'.
~ T The result of our two telephone conferences was a tentative agreenent by the staff that B&W could meet the cold-shutdown requirements for BSAR-205 __ _ _ _
at the PDA stage by (1) adequately describing the available system design features and S&W commit:nents to future work relevant to each of our seven criteria, and (2) by also specifying, through interface criteria, those design features, potentially necessary manual actions, or operational procedures which will be the responsibility of a referencing applicant.
You are urged to address each of the seven requirements of'the Enclosure at the earliest possible time. This : natter is the critical path work item in our effort to complete the Safety Evaluation Report and PDA work on the BSAR-205 project.
Sincerely, l
Original Signed by, i
O. D. Parr Olan O. Parr, Chief Light Water Reactors Branch 'to. 3
'i Division of Project %nagement i
Enclosure:
l
}
Requirements for BSAR-205 Project Compliance l
with Staff Cold Shutdown Criteria i
CC W/ enclosure:
I i aed.iu i. e44e p
)...
LWR #3 L
[
LWR..#3:gC_
l mCox/LL y n ggp[p,.
0 j
f 01 /78 _F i 178 47 /./78 f
.m m m n...o =.
u---.-...---
v
- +
en
f, n
(.
Babcock & Wilcox Ccapany
-3 MAY 011978 cc: Wasnington Public Power Supply System ATIN: tir. N. O. Strand Managing Director (Acting)
P. O. Box 968 3000 George Washington Way Ricnland, Washington 99352 Mr. Robert Botsum Bethesda Representative Baocock & Wilcox Nuclear Power Generation Division Suite 5515, 7735 Old Georgetown Road Bethesda, Maryland 20014 O. G. Shultz Project Engineer
,, t.,
Stone & Weoster Engineering Corporation P. O. Box 2325
's, Boston, Massachusetts 02107 i
1
- Mr W..E. Kessler Ccanonwealtn hssociates, Inc.
209 East Washington Jackson, Michigan 49201 Robert J. Kafin, Esq.
115 Maple Street Glen Falls, New York 12801 1
Mr. B. M. Miller Ohio Edison Company I
76 South Main Street Akron, Ohio 44308 9
i
\\
f i
)-
w.j
\\
..-..,,-...-.--,-.,--,-.-~------:
- -.,..v.~-r--,--------
~
m _._ _
]
NAY 0 ) 1978 ENCLOSURE Requirements for BSAR-205 Project Comoliance with Staff Cold Shutdown Criteria i
l 1.
Provide safety-grade steam generator dump valves, operators, air and power supplies which meet the single failure criterion.
2.
Provide the capability to cooldown to cold shutdown assuming the most limiting single failure in less than 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> or show that manual actions inside or outside containment or return to hot standby until the manual actions or maintenance can be performed to correct the failure provides an acceptable alternative.
3.
Provide the capability to depressurize the reactor coolant system with only safety grade systems assuming a single failure, or show that manual actions inside or outside containment or remaining at hot standby until manual actions or repairs are complete provides an acceptable alternative.
4.
Provide the capability for boration with only safety grade n
systems assuming a single failure or show that manual actions
(
)
inside or outside containment or remaining at hot standby until manual action or repairs are completed provides an acceptable alternative.
l S.
Provide the system and component design features necessary for the prototype testing of both the mixing of the added barated i
water and the cooldown under natural circulation conditions with and without a single failure of a steam generator atmospheric dump valve. These tests and analyses will be used to obtain infonnation I
on cooldown times and the corresponding AFW requirements.
6.
Coninit to providing specific procedures for cooling dcwn using ll natural circulation and submit a summary of these procedures.
7.
Provide or require a seismic Category I AFW supply for at least 1
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at Hot Shutdown plus cooldown to the DHR system cut-in j
based on the longest time (for only onsite or offsite power and assuming the worst single failure), or show that an adequate i
alternate seismic Category I source will be available.
r' l
V i
1 n__~
.--,...,--an.....~~
..--.-m>..m-,_.w.-..
.---.~--.--n
..e
~ ~~ -
~.s
-.~.s~
~
N.x D x-m 50 No. STN Docket Wilcox Co pany m
lr Mr. James H. Tay o of Licensingration Division Babcock ATTN:
Manager ne SHUTDOWN Nuclear Power Ge 24505 COLD P. O. Box 1260Lynchburg, Virg REGARDING FOR inia CAF BILITY ds in Reactor Safeguara generic basis, ISSUE Geritlemen: OUTSTANDING DESIGN heat on on considering, transf erringthe transition BSAR 205 Comittee from SUBJECT :OF nly to the Advisory for ing o were vided cold shutdown, usf ailure has onsite that weld be pro during our Repo t stated or r
capability shouenvironment,offsite 77,we to reactor to theoperating condituming (1) onlylimiting In 19 ions July the of such r
whethe might requiref-plant portions systems, and assand (2) the most vide from thenormal reactor to pro that we modified of the balance-oBSAR 205 to be final iew gradeavailable stated decision safety also power is s
We occurred.and the design referenility.
to the ACRS, Requirements Reve Chairm a
cing an, design applications capab mittens, dated port r RegulatoryE. G. Case, Co following our Re wn cold shutdo that specific ratio was taken by oumemorandum from overall plantDesign Appro val Director for Opeestablished riod the pematte which in r
inco poratedrmit or Prelim 1,1978, an ina y for In on th sComittee, in ick, ExecutiveTh s decision This r
i a
r i
be shall to L. V. Goss16, 1978uirementsnstructioDesign Appromit applicat ary by fore January n pe cted after Janu Februarytechnical req Preliminary wh ch core docketed be expe i
AR 2052 construct on per is i
for ance designs we thers, the BS issu ns applicatio nse nd lice 1a operat ngincludes, among oon Company.
the ERIE i
and applicationthe Ohio Edis me=*--
, na J
/
y J
~
,f f
- \\
UNITED STATES
?, )
NUCLEAR REGULATORY COMMISSION e
i WASHINGTON, D. C. 20555 1+,......
i AIAY 011978 Docket No. STN 50-561 f
- h Babcock & Wilcox Company i
ATTN: Mr. James l1. Taylor Manager of Licensing Nuclear Power Generation Division
}
P. O. Box 1260
.,i Lynchburg, Virginia 24E05 Gentlemen:
N
SUBJECT:
OUTSTANDING ISSUE REGARDING CAPABILITY FOR COLD SHUTDOWN 0F BSAR-205 DESIGN In our Report to the Advisory Comittee on Reactor Safeguards in
<U July 1977, we stated that we were considering, on a generic basis.
whether the capability should be provided for transferring heat i
from the reactor to the environment, during the transition from f
nomal reactor operating conditions to cold shutdown, using only safety grade systems, and assuming (1) only offsite or onsite power is availabic and (2) the most-limiting single failure has I
occurred. We also stated that we might require the BSAR-205 design and the designs of the balance-of-plant portions of applications referencing BSAR-205 to be modified to provide such cold shutdown capability.
In the period following our Report to the ACRS, a final decision on this matter was taken by our Regulatory Requirements Review t
Comittee, in a memorandum from E. G. Case, Committee Chainnan, to L. V. Gossick, Executive Director for Operations, dated i
February 16, 1978. This decision established that specific technical requirements shall be incorporated in overall plant designs for which construction permit or Preliminary Design Approval applications were docketed before January 1,1978, and for which i
operating license issuance is expected after January 1,1979. This i
i includes, among others, the BSAR-205 Preliminary Design Approval (PDA) i application and the ERIE 1 and 2 construction permit application by the Ohio Edison Company.
i i
i
.. \\
~
T)w 0- ^W m -
1 7
MAY 011978 Babcock & Wilcox Company,
Our specific technical requirements for plants referencing the BSAR-205 design were transmitted to Mr. J. Lauer of your staff by telecopy on April 10,1978. These requiremer:ts are included in the Enclosure.
In two " working level" telephone conferences on April 21 and April 27, our respective staffs have discussed the degree to which the BSAR-205 Preliminary Safety Analysis report documents compliance with, or provides information necessary for referencing applicant compliance with, our seven reqcirements for cold shutdown capability.
We indicated to your staff that your formal comitment to our requirements'.
would satisfactorily complete your response to the cold shutdown issue at the PDA stage of review. However, your staff noted that the alternatives to-safety grade equipment,- as stated in items 2,- 3, and 4 of our require-ments, were at least partly within a referencing applicant's design scope.
Further, your staff stated that it would be difficult for B&W to comit to the requirements as written because of the non-quantitative nature of the allowed alternatives, e.g., "...or show that manual actions inside or outside containment or return to hot standby... provides an acceptable i
alternative".
j The result of our two telephone conferences was a tentative agreement by the staff that B&W could meet the cold-shutdown requirements-for BSAR-205 at the PDA stage by (1) adequately describing the available system. design -
features and B&W comitments to future work relevant to each of our seven writeria, and (2) by also specifying, through interface criteria, those design features, potentially necessary manual actions, or operational procedures which will be the responsibility of a referencing applicant.
You are urged to address each of the seven requirements of the Enclosure i
at the earliest possible time. This matter is the critical path work
=. ;
item in our effort to complete the Safety Evaluation Report and PDA -
work on tha BSAR-205 project.
Sincerely,
[
N&
I an. Parr, Chief Light Water Reactors Branch No. 3 Division of Project Management
Enclosure:
Requirements for BSAR-205 Project Compliance with Staff Cold Shutdown Criteria f
cc w/ enclosure:
(3 See next page
)
V j
l
-.-._.s
- ~
MAY 011978 m
\\
ENCLOSURE Requirements for BSAR-205 Project Compliance with Staff Cold Shutdown Criteria 1.
Provide safety-grade steam generator dump valves, operators, air and power supplies which meet the single failure criterion.
2.
Provide the capability to cooldowr to cold shutdown
- assuming the most limiting single failure in less than 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> or show that manual actions inside or outside containment or return to hot t
standby until the manual actions or maintenance can be performed to correct the failure provides an acceptable alternative.
J3.-
Provide the capability to depressurize-the reactor-coolant system with only safety grade systems assuming a single failure, or show that manual actions inside or outside containment or remaining at hot standby until manual actions or repairs are complete provides ar. acceptable alternative.
I 4.
Provide the capability for boration with only safety grade g
systems-assuming-a-single-failure-or show -that manual actions inside or outside containment or remaining at hot standby until manual action or repairs are completed provides an acceptable alternative.
5.
Provide the system and component design features necessary for the prototype testing of both the mixing of the added borated water and the cooldown under natural circulation conditions with and without a single failure of a steam generator atmospheric dump valve. These tests and analyses will be used to obtain information on cooldown times and the corresponding AFW requirements.
__ _~~~' '
6.
Commit to providing specific procedures for cooling down using natural circulation and submit a summary of these procedures.
7.
Provide or require a seismic Category I AFW supply for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at Hot Shutdown plus cooldown to the DHR system cut-in based on the longest time (for only onsite or offsite power and assuming the worst single failure), or show that an adequate alternate seismic Category I source will be available.
4
-l s
1 i
l As e e
--e.g-
_ ww a wwy
- m
UNITED ETATES NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20555 301-492-7000 FACSIMILE SERVICE REQUEST DATE: 08 O/ 77 NEsSAcE TO: T/ odd =76-.
TELECOPY NUMBER:
h04.3[fY E 7~773 AITIONATIC:
No VERIM CAn ON NUMBER 80Y-388["I///
X J2.7 4 7 -
No. OF PAGES 3
PLUS INSTRUCn0N SHEET
/_VAkWBdf6,1/,#.
sr4TE & Cirr H7.SSAGE FRON:
QY TELECOPY NUMBER 301-492-8110 RAPIFAX AITIOMATIC 301-492-7617 3M VRC Attr0HATIC VERIFICAn CN NUMBER 301-492-7371 BUILDINC 8
0FFICE PHONE cQ.724 3 MAIL STOP
/2h CIASS OF SERVICE:
Overnight 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 2 hour 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> M Innediate SPECIAL INSTRUCriONS:
&&A14L.
\\
Received / Time-Date Transmitted / Time-Date g,
.Z ] c f.
%,g '
q
.g, 4
& ;l}
9
- -