ML18086A860
| ML18086A860 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/31/1981 |
| From: | Ross W Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8108130135 | |
| Download: ML18086A860 (5) | |
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Docket Nos. 50-272 and 50-31 l DISTRIBUTION Docket
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SUMMARY
OF MEETING HELD ON JULY 23, 1981 HIT!-! THE LICENSEE TO DISCUSS THE LICENSEE'S REQUEST FOR EXEMPTION FROM 10 CFR PART 50 APPENDIX R (FIRE PRO-TECTION)
By letter dated March 19, 1981 the licensee requested four exemptions from Appendix R.
This meeting was called to discuss the staff's request for fur-ther justification for one of these exemption requests, i.e., the need for automatic fire suppression systems in addition to 1-hour fire barriers -
(Paragraph III.G.2.c).
A list of attendees is attached.
The licensee exolained that only a ~wief justification for this exemption req'uest had been provided in the March 19, l 981 1 etter because the use of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> fire barriers without fire suppression systems ( or 1/2 h.otJrffiiTe barri~r,s with fire suppression sysmems) had been previously approved by the staff ii1 its Fire Protection SER.
The staff acknow1 edqed the results of the earlie~ ~eview bUt advised the licensee that 10 CFR 50:48 requires a re-review of this subject using Appendix R crite~ia. Under these conditions, a blanket exemption cannot be considered; however9 the staff will consider specific exemption requests for relief from the requirements of Paragraph III. G. 2 for individually defined areas.
For each a~ea it is the licensee 1s responsibility to show that, under a fire condition, there is high assurance that safe shut-down Cf.ln be achieved with the available undamaged equipment.
The licensee suggested that the following considerations could be used to augment the single justification {i.e., the fire loading is less than 1/2 hour) given in the March 19, 1981 letter:
(1)
The Salem Fire Brigade can respond and extinguish a fire in -40 minutes; thereby leaving a 20 minute margin when a 1-hour fire barrier is pre-sent.
(2)
Fire if,oads of 15 minute duration are assumed for notrnal loading and loads
<30 minutes are -assumed for transient combustibles.
(3)
The ASTM-19 criteria were deV.,~lppAd for plants with more combustible componen-~s than n9c.lear-__noi.-1e~ilnts __ arul_ are too stringent~?for plants such as Sal em.
- 8108130135 810731*,
PDR ADOCK 05000272 F
PDR OFFICE.........................
SURNAME.........................
DATE.........................
NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-335-960
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.. {4) f Passive fire barriers 'are not subject.to faHiure mechanisms that are exhibited by mechanical (suppression) systems.
(5) The type of electrical cable used at Salem will not propagate a fire.
(6) A single test run on 4.kv ~able by the licensee showed that the cable's functional capability was mainM:i.ned for l lJ minutes when the cable was heated in a furnace at temperature that were equivalent to that seen by a cab~)e enclosed an a 1-hour barrier subject to a ASTM-19 test fire. The cable failed when its temperature was 620°F.
The licensee believes that the resu1tsof this test was conservative because the cable faned at the exposed ends.
- A more accurate test will be designed; The staff adv*ised the licensee to submit further justification for exemptfi.ons from instal'Tation of automatic fire suppression systems on an area by area basis.
This information (vill be revieweq against the requirements of Appen-dix R on the basis of equivalent protection in each area. The licensee was cautioned that several of its proposed justifications have potential weak-nesses 9 i. e. ;
(a) field experience may differ from test results~
{b) transient combustibles may not be properly controlled by administrative
- means, (c) some types of passive barriers are subject to failure other than from fire damage (degradation of Kaowco l by high pressure water from fire hoses).
(d) location of barriers may provide sufficient protectio~ on one side but not tM1e'~othet?\\,~..
(e) height of barrier may be insufficient to protect equipment above the barrier.
The staff also requested that if be allowed to review the procedures of future reliability tests before the tests are performed.
The licensee agreed.
The licensee corrmitted to provide~ within one week, a schedule for:
(a) sub-mittal of additional informat'ton on the scope of the review needed to identify area-specific exemptions from automatic suppression systems (including an example of one area) and (b) submittal of the remtd.nder of the area-specific analyses.
The staff cautioned that time is 'i:mportant beGause of the Commission's instruc-tion that Appendix R requirements to be impl ementec! by February 1982.
OFFICE.........................
SURNAME~ ************************
DATE.........................
NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-335-960
-- During this meeting the 1icens~e also advised the staff that :adi:liti*onah~in formation would soon be submitted related to exemptdion request #3 of the ;',~re:,
March 19, 1981 letter.* As the result of the staff's site visit in May 1981 the licensee has agreed to supplement the redundant sprinkler system in the amcil iary feedwater pump area with 1-hour barriers for:* the turi.ifoe-driven pump.
This additional protection has been approved by the staff and will be sufficient to eliminate the need for an exemption.
I&E will assure that these barriers are installed.
W. J. Ross, Project Manager Operating Reactors Branch #1, Dl OFFICE~... ~~~!.]~ :.o
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Mr. F. W. Schneider Public Service Electric and Gas Company cc:
Mark J. Wetterhahn, Esquire Conner, Moore and Corber Suite 1050 1747 Pennsylvania Avenue, NW Washington,. D. t. 2000&
Richard Fryling, Jr., Esquire Assistant General Solicitor Public Service El ectri C' and Gas Company 80 Park Place Newark, New Jersey 07101 Gene Fisher, Bureau of Chief Bureau of Radiation Protection 380 Scotch Road Trenton, New Jers~~. 0.8628 _
Mr. R. L. Mittl, Ge.neral.Manager Licensing and Environment Public Service Electric and Gas Company 80 Park Plaza 17C Newark, New Jersey 07101 Mr. Henry J. Midura, Manager Salem Nuclear Generating Station Public Service Electric and Gas Company P. O. Box 168 Hancocks Bridge, New Jersey 08038 Salem Free Library 112 West Broadway Salem, New.Jersey 08079 Leif J. No~rholm, Resident Inspector Salem Nuclear Generating Station U.* S. Nuclear Regulatory Commission Drawer I Hancocks Bridge, New Jersey 08038 John M. Zupko, Jr~, Manager Nuclear Operations Support Public Service Electric and Gas Company so Park Plaza - lSA Newark, New Jersey
- 07101 Mr. R. A. Ude.ritz General Manager, Nuclear Production Public Service Electric and Gas Company 80 Park Plaza 15A Newark, New* Jersey 07l0l Mr. J. T. Boettger General Manager, Quality Assurance I&E Public Service Electric and Gas Company 80 Park Plaza Newark, ~Jew Jersey 07101 Mr. Edwin A. Li den, Manager*
Nucl-ear Licensing Licensing and Environmental Dept.
Public.Service Electric and Gas Company 80 Park Plaza 160 Newark, New Jersey 07101
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ATIENDEES Meeting Between NRC Staff and PSE&G 7/23/81 NRC
- w. J. Ross G. c. Meyer
- v. Benaroya R. H. Vollmer R. L. Ferguson T. V. Wambach
- w. Johnston B. Cohn (Gage-Babcock Assoc.)
PSE&G R. L. Mittl R. A. Schauffler (Proto-Power)
J. P. Gagliardi W. Gailey G. W. Supplee W. Pavinci ch