ML18082B211
| ML18082B211 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/29/1980 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Mittl R Public Service Enterprise Group |
| References | |
| NUDOCS 8009220050 | |
| Download: ML18082B211 (13) | |
Text
AUG 2 9 1980 Docket No. 50-311 Mr. R. L. Mittl, General Manager Licensing and Environment Engineering and Construction De.partinent'
- Pub 1 i c Service Electric and Gas CompanY *
- 80 Park Place Newark, New Jersey 07101
Dear Mr. Mittl:
DISTRIBUTION Docket.
NRC PDR-LOCAL PDR, LB#3 Reading NRR Reading JKerriga-n ASchwencer Jlee
- OELD~*X~
- OI&E(3.)
ACRS(l6)
- TERA* **
NSIC DGEisenhut RAPurple RTedesco
SUBJECT:
REQUEST FOR ADDITIONA_L_ tNFORMATI,9N QN SA.L.EM, U,NIT _NO *. ?
As a result of our continuing review of SaJem 2 for a full power license, we find that we need addition al i rifornia ti on to comp i ete ou'r 'ev'a 1 u'at ion.
The specific information required* is. lfated in the en.closures. Thfa information was previously telecop'ie*a. "tp._inembers"-of' your* starf~..
.*~
To maintain a timely review for the Salem 2 full power license, we will need your response as soon as *oassfble-but no later than September l, "*
1980.
This date is consistent.with 'the commitments made fo yol.i'r letter*
dated August 19, 1980, with the* ejtceptio*ri* *o*f your* coffiinitmer1t to. -*
provide information on turbine.d.iscs.:* "t-ie \\*iish 'to _emphasize that-.tfris **
information must be provided p.r'iC>r* to £D~side~atio~_ o_f a. full po~~e*r ;....
operating license for Salem, Unit No. 2. - If you have any questions.
about this request, contact the.. __ ~a'lem" 2: proJecf manager, Janis.Kerrigan...
on (301) 492-7272..
Enclosures:
As stated cc w/encl:
See next page NRC FORM 318 (9-76) NRCM 0240 Sincerely~
Original signed by
'Robert L. Tedesco Robert L. Tedesco, for Licensing Division of Licensing
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1'.'.:l'u.s. GOVERNMENT PRINTING OFFICE: '1979-289-369
AUG 2 9 1980 Docket No. 50-311 Mr. R. L. Mittl~ General Manager Licens1ng and Env1rol'lftlent Engineering and Construction Depa.rtmerif~-- -
Pub 11 c serv1 ce E1 ectr1 c and Gas C~ni -..
80 Park Place Newark, New Jersey 07101
Dear Mr. M1ttl:
DISTRIBUTION Docket.
NRC PDR*
LOCAL PDR LB#3 Reading NRR Reading JKerrigan ASchwencer JLee OELDUi
- OI&E(3).
ACRS-( 1 6-}
- TERA--
NS IC DGEi sen hut.
RAPurple RTedesco
SUBJECT:
REQUEST FOR ADDITIONAL_ I!~FORMATI9H ON SALEM, UNIT NO. 2 As a result of our conUnufng review of Salem 2 for a full power 1 icense, we find that we need addftfonal 1nfonnat10n to complete our Erialuation.
The specific infonnat1on required Js_ 1_1sted in. t}'le enclosures._ This information was pretiously te1e~op1eEi. to ~rs 01' yo~r ~taff._
To maintain a timely review fo_r ~~.. SaJ!!D 2 full powei: lice~e, we will_*
need your response as. soon as possibl~ but no later than September 1, 1980.
This date fS consistent *with the Camrftments made in your letter dated August 19. 198th. with the ex"Cept1on-*of your *cOOinitmel;t to provide infonnation on turbine __ i:Hscs.~-w~-wis"fi_ tj) ~hasize *that -t~is-_
- infonnation must be provided prior to consideration of a full power operating license for Salem, Unif f{o. __ 2~. _ If j~ h_ave any_ questions - *
- abou(t this request. contact the_ Sal.~ ?. pr_oJ.~. _ma~ageY',_ J_a_nis Kerr_igan ___.
on 301) 492-7272.
Enclosures:
As stated cc w/encl:
See next page Sincerely,_
Original signed by
- Robert L. T ed~sco Robert L. Tedesco, Assistant D1!ec_tpr for Licensing 01v1sfon of U censing
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- *1**************,**-i-********.. *****..
................. *!*................ *1*................
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NRC FORM 3!a (9*75) NRCM J2.1Q
- U.S. :iO'I ER NM ENT "RI NT! NG *'.)FFICE: 1979-289*369
UNITED ST A TES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Docket No. 50-311 Mr. R. L. Mittl, General Manager Licensing and Environment AUG 2 9 1980 Engineering and Construction Department Puplic Service Electric and Gas Company 80 Park Place Newark, New Jersey 07101
Dear Mr. Mittl:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON SALEM, UNIT NO. 2 As a result of our continu1ng review of Salem 2 for a full power license, we find that we need additional information to complete our evaluation.
The specific information required is listed in the enclosures. This information was previously telecopied to members of your staff.
To maintain a timely review for the Salem 2 full power license, we will need your response as soon as possible but no later than September l, 1980.
This date is consistent with the commitments made in your letter dated August 19, 1980, with the exception of your commitment to provide information on turbine discs.
We wish to emphasize that this information must be provided prior to consideration of a full power operating license for Salem, Unit No. 2.
If you have any questions about this request, contact the Salem 2 project manager, Janis Kerrigan on (301) 492-7272.
Enclosures:
As stated cc w/encl:
See next page Sincerely, Robert L. Tedesco, Assistant Director for Licensing Division of Licensing
Public Service Electric & Gas Company ATTN:
Mr. R. L. Mittl cc: Richard Fryling, Jr., Esq.
Assistant General Counsel Public Service Electric & Gas Company 80 Park Place Newark, New Jersey 07100 Mark Wetterhahn, Esq.
Conner, Moore & Caber Suite 1050 1747 Pennsylvania Avenue, N. W.
Washington, o. C.
20006 Mr. Leif c/o u. s. Nuclear Regulatory Corrmission Region I, Drawer I Hancocks Bridge, New Jersey 08038 AUG 2 9 1980
REQUEST FOR ADDITIONAL INFORMATION UPGRADED METEOROLOGICAL PROGRAM ENCLOSURE l
- Since the Salem SER was written (October 1974)~ NUREG-0654, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 11 has been issued.. A de-scription of and completion schedule for an upgraded meteorological program in subs tan ti.a 1.- compliance with NUREG-0654, Appendix 2 is required by NUREG-
- 0694, 11TMI-Related Requirements for New Operating Licenses 11 before issuance of a full power license.
The essentiaLelements of the NUREG-0654, Appendix 2 criteria are:
- 1.
A primary* meteorological measurements program with redundant power sources.
- 2.
A backup meteorological measurements program with redundant power sources..
- 3.
A system for making real-time predictions of the atmospheric effluent transport* and diffusion, including Class A and Class B models as de-scribed.. in Appendix 2.
- 4.
A capability for remote interrogation on demand of the atmospheric measurements and prediction systems by the licensee, emergency response organizations, and the NRC staff with primary and backup communications systems.
The presently.available Salem Emergency Plan, submitted July 12, 1980, provides ve.ry limited information on the emergency meteorology pr.ogram which is not responsive to the requirements in NUREG-0694 for a full power license.
We require that PSE&G commit to incorporating these essential elements in their emergency meteorological program and provide a completion schedule for each element.
Enclol.e 2 REQUEST FOR INFORMATION RELATED TO TURBINE DISCS I.
P~vide the foll0wing information for*each LP turbine:
A.
Turbine type B.
For each disc:
- l. type of material including material specifications
- 2.
tensile properties data
- 3.
toughness properties data including Fracture Appearance Transition Temperature and upper energy and temperature
- 4.
keyway temperatures
- 5.
cr1tieal crack size at operating and design overspeed crack growth rate
- 7.
calculated bore and keyway stress at operating and design overspeed
- 8. calculated Kie data
- 9.
minimum yield strength specified for each disc II. Provide details of the results of any completed preservice inspection of LP turbine rotors.
For each indication detected, provide details of the location of the crack, its orientation, and size.
III. Indicate discs that will have sufficient moisture in the hub to cause a pro-pensity for stress corrosion cracking..
IV. *Indicate whether an analysis and evaluation regarding turbine missiles has been perfonned for your plant and provida:i to the staff. If such an anaTYsis and evaluation has been perfonned and reported, please provide appropriate references to the available documentation.
In the event that such a study has been made, consideration s-hotJld. be gtven to schedultng such an action.
ENCLOSURE 3 REQUEST FOR ADDITIONAL INFORMATION CONTAINMENT PRESSURE BOUNDARY FRACTURE TOUGHNESS We require the following information:
- 1.
Identification of the fabrication codes (edition and addenda) and the specific* paragraphs in these codes that specify the fracture toughness requirements and acceptance criteria (for weldments and base metals).
Codes and code paragraphs should be identified for all materials which constitute part of the containment pressure boundary (e.g., free stand-ing ves-sel, piping penetrations, personnel airlocks, equipment hatch);
- 2.
The materials test data that certify that the fracture toughness acceptance standards have been met for each of the identified materials in the containment pressure boundary;
- 3.
The containment lowest service metal temperature;
- 4.
As built,dimensi.ons and material of construction of the penetration sleeve and canopy seal welded to the process pipe and sleeve as shown in your FSAR, Figure 5.2-38.
REQUEST FOR ADDITIONAL INFORMATION CLADDING SWELLING AND RUPTURE MODELS ENCLOSURE 4
= -T>te'NRC staff-has been generically evaluating three materials models that
- are used in ECCS evalua~ions. Those models predict cladding rupture temperature, cladding burst strain, and fuel assembly flow blockage, We have (a) discussed our evaluation with vendors and other fodustry repre-sentatives (Reference 1), (b) published NUREG-0630, "Cladding Swelling and Rupture Models for LOCA Analysis" (~ference 2), and (c) required licensees to confirm that their operating reactors would continue to be in conformance with 10 CFR 50.46 if the NUREG-0630 models were substituted for the present materials models in their ECCS evaluatfons and certain other _compensatory model changes were allowed (References 3" and 4).
Until we have c_ompleted our generic review and implemented new acceptance criteria for cladding models, we will require that the ECCS analyses in your FSAR be accompanied by supplemental c13lculations to be performed with the materials models of NUREG-0630.
For these supplemental calculations only, we will accept other compensatory model changes that may not yet be approved by the NRC, but are consistent with the changes allowed for the confirmatory operating reactor calculations mentioned above.
Please provide the supplemental calculations described above.
i I
ENCLOSURE 5 REQUEST FOR ADDITIONAL INFORMATION
. RELIEF AND SAFETY VALVE TEST REQUIREMENTS
- 1.
PSE&G should conmit to monitor the EPRI program to provide assurance that:
(a)
(b) it will be applicable to the Salem plant design, and
.. it will provide sufficient information to qualify Salem's reactor coolant system relief and safety valves and associated pip!ing and supports under expected operating conditions for
- .design basis transients and accidents.
- 2.
PSE&G should cominit to submit to NRC by July 1, 1981 the following information with respect to Salem:
(a).
Evidence supported by test of safety and relief valve function-ability for expected operating and acctdent (non-ATWS} condi-tions.
The testing should demonstrate that the valves will open and reclose under the expected flow conditions.
(b)
Since it is not planned to test all valves on all plants, PSE&G must $.Ubm.it a correlation, or other evidence, to subs tan ti ate that the valves tested in thefliPRol*program*:demonstrate function-ability of as-installed primary relief and safety valves.*
Thfs correlation must show that the test conditions used are eq~ivalent to expected operating and accident conditions as prescribed in the FSAR. *The effect of as-built relief and safety valve discharge piping on valve operability must also be accounted for, if it is different than the generic test loop piping.
le}
Test data i.ncluding criteria for success and failure of valves tested.must be provided for review and evaluation. This test data should include data which would permit plant specific evaluation of discharge piping and supports which are not tested* directly.
- 3.
PSE&G sh.cul d commit to submit Ely January l, 1982 evidence supported 5.y tes~* to qualify Salem~s block valves under expected operating conditions for design 5asis transients and accidents.
e e
- ENCLOSURE 6 REQUEST FOR ADDITIONAL INFORMATION Q-LIST I. The following items from the Q-list (FSAR Appendix C) need expansion and/or clarification ~s noted.
Revise the list as indicated or justify not doing so.
- l. Pages D.2-i2 and D.5-13 of the Salem FSAR QA programdescription states that the structures, systems, and components covered by the quality assurance program are identified in FSAR Appendix C.
We believe that
'this statement is incorrect.
The statement should be applicable only to those items categorized as Class I.
In'this regard, we note that the cooling loop of the Spent Fuel Pool *cooling System is Class II and should be Class I. However, the remaining structures, systems, and components in Class II and Class III are not normally within the scope of Appendix B.
Please redefine the items within the scope of Appendix B.
- 2.
The items entitled Service Water Screen Well should be clarified to include
- the entire intake structure.
3~ Identify those portions of the Chemical and Volume Control System that are within the scope of Appendix B (e.g., Emer11encv Roration Svstem - Boron injection surge tank, filter, etc.).
4..
Identify those portions of the Service Water System that are within the scope of Appendix B (e.g., service water pumps, automatic.control shut off valves, piping, etc.).
- 5.
We have assumed that for all items identified as Class i in Appendix B, the entire structure, system, or component is within the scope of Appendix B~ If this is not the case, clearly-identify each portion of the*Cl.ass I structure, system, or component not within the scope of Appendix B.
- 6.
Clearly identify any yard structures and ~omponents that ar.e within.the scope of Appendix B (e.g., emergency condensate storage tank, dikes, etc.). *
- 7.
Clarify all portions of the Reactor Containment and Containment Auxiliary Structures that are within the scope of Appendix B {e.g., pipin~, ducts and electrical penetrations, personnel access hatch, equipment access hatch, all containment isolation valves, containment sump, sump screen, and vortex suppression devices).
Jr, The following items do not appear on the Q-list (FSAR Appendix C).
Add the following items to the list or justify not doing so:
- 1.
Fuel Handling System.
- 2.
Control panels - Class IE circuits.
- 3. Steam Supply System.
- 4.
Those "portions" of th~ radiation mo~itoring system *required for Class I equipment and systems {Ref.:. Appendix C).
.. 5.
Process Instrumentation and Control System.
6~ Ventilation systems for the switchgear room, diesel generator area, auxiliary and fuel handling building.*
- 7.
Feedwater System extending from the steam generators up to and including.
the outermost containment isolation valve and connected piping of 2 1/2 inches or larger nominal pipe size up to and including the first valve (including a safety or relief valve) that is either normally closed or capable of automatic closure during all modes of normal reactor operation.
- 8.
As in 7 above for.the Main Steam System, including Main Steaml ine Safety Va lve*s and Steaml foe Power-Operated Relief Va ives, Main Steam Piping-Steam Generator to Main Steam Isolation Valve.
- 9.
Cooling-loop-of the.Spent Fuel Pool Cooling System.
- 10.
Non-safety systems which penetrate containment and are therefore an exten-sion of the containment boundary, up to and including the containment isolation valve.
- 11.
Steam Slowdown System extending from the steam generators up *to and including the outermost containment isolation valve.*
- 12.
Sampling System extending from the reactor coolant system or other safety system up to and including the.outermost containment isolation valve.
. 13.
Instrument Air System (accumulators, interconnecting piping and valves) for air-operated valves in systems that perform a safety function. -
- 14.
The Diesel Generator Building.
- 15.
Meteorological data collection programs.
- 16.
Dike for protecting the facility from excessive wave action.
- 17. Containment Vacuum System.
- 18.
Containment Atmosphere Cleanup System.
- 19.
Recirculation Spray Subsystem.
- 20.
Onsite Power Systems (Class IE)
(1). Diesel generator packages including auxiliaries (e.g., lube system, jacket cooling, air start system, governor, voltage regulatory, excitation system).
- 21.
4160 volt switchgear.
22.. 480V load centers.
- 23.
Instrumentation, control, and power cables (including underground cable system, cable splices, connectors, and terminal blocks).
~.
- 24. Cond~it and cabl* trays and their supports.
_Note - Raceway installations containing Class IE cables and other raceway installations required to meet seismic Category I requirements (those whose failure during a seismic event may result in damage to any Class IE or other safety-related system or components).
- 25.
Transformers.
- 26.
Valve operators.
- 27.
Protective relays and control panels.
- 28.
AC control power inverters.
- 29.
120 AC vital bus distribution equipment.
- 30. Containment electrical penetration assemblies.
- 31.
Other cable penetrations (fire stops).
- 32.
(1) Batteries, battery chargers, and distribution equipment.
(2) Cables.
(3) Conduit and cable trays and their supports.
(4)
Battery racks.
(5) Protective relays and control panels.
- 33.
Quench Spray Subsystem.
- 34. Air Conditioning System (control, equipment, and cable room).
35.. Emergency Diesel Auxiliary Systems.
- 36. Spent Fuel.Cooling System.
- 37.
Nuclear Instrumentation System (source or intermediate range neutron flux monitors).
- 38.
4KV Auxii iary Power-sy"stem-. *
- 39.
600V Essential Auxiliary Power System.
- 40.
125V DC Vital Instrumentation and Control.
- 41.
Leak Detection System (as discussed in FSAR Section 4.2.7).
- 42. Missile Barriers (protecting safety-related equipment).
'1'
- 43.
- PORV Block Valves.
- 44. Pressurized Relief lines (piping from the pressurizer to pressurizer drain tank).