ML20236Y131
| ML20236Y131 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/25/1986 |
| From: | NRC |
| To: | NRC |
| References | |
| TAC-60953, NUDOCS 8712110117 | |
| Download: ML20236Y131 (13) | |
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ATTACHMENT 1, Move RCIC-V-64 from section a. Automatic Isolation Valves to section c. Manual Containment Isolation Valves of Technical Specification Table 3.6.3-1 (pgs. 6-24 and 6-27).
- 2. . Correct the EPN's for PI-EFC-X29b/d, X29e/f, X30d/f, X42e/f and X69d/f to the MEL listings of PI-EFC-X29d, X29f, X30a, X42f and X69f (pg. 6-24).
- 3. Under section b. Excess Flow Check Valves, move PI-EFC-X66, X67, X82b, X84a and X119 from the listing of Reactor Pressure Vessel and PI EFC-X86A, X86B, X87A and X87B from the listing Other to Containment Atmosphere (pgs. 6-24, 6-25 and 6-26).
- 4. Add PI-EFC-X8 to the list of Excess Flow Check Valves associated with the Reactor Pressure Vessel. This valve was inadvertently omitted from the Technical Specification table; however, it is e included in Surveillance Procedure 7.4.6.3.4.1 and, therefore, this change does not constitute a safety concern (pg. 6-25).
- 5. Add CAS-V-730 to section c. Manual Containment Isolation Valves and delete the listing of Containment Air Supply, CAS-V-453, from section d. Other Containment Isolation Valves. CAS-V-730 was added to the system via a PED and replaces CAS-V-453 as the outboard CIV for penetration X-82e (pgs. 6-26 and 6-31).
- 6. Add notes (g) and (b) after RCIC-V-742. This valve is a sample isolation valve on the head spray line and will be hydro tested with RCIC-V-13 and 66 (pg. 6-27).
- 7. Move RHR-V-124A,124B,125A and 125B from section d. (pg. 6-30) to section c. (pg. 6-27). These valves are now Manual Containment Isolation Valves.
- 8. Correct the typo on page 6-29 by changing RCIC-B-68 to read RCIC-V-68. '
- 9. Delete RFR-RV-55A, B from page 6-29 and RHR-RV-95A, B from page 6-30. These valves have been removed from the system.
- 10. Add a new listing to section d. for Radiation Monitoring. PI-EFCX-72f f and 73e are Containment Isolation Valves and were previcusly omitted from this table (pg. 6-32). ;
- 11. Correct the referenced Technical Specification in note (g) (pg. 6-32) from 4.4.3.2d to 4.4.3.2.2.
NOTE:
The current revision of Surveillance Procedure 7.4.6.1.2.4 for Local Leak Testing takes into account the changes inade in s teps 5, 6, and 10; therefore, these changes do not constitui.e a safety concern.
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. 12. Correct TIP system containment isolation valve (CIV) EPN's (pg. 6-22 and 6-32) per DCP 84-1672-0A. Delete TIP-V-11 from the Table (pg. 6-'22); this valve is not a CIV.
( TIP-V-6, the N,, purge supply check valve, is the CIV. Add note e) to indicate exemption from Type C leak rate testing for the TIP shear valves as previously approved in FSAR Table 6. 2-16.
- 13. Add note j) to Table 3.6.3-1 for RCIC-V-8, RCIC-V-63, RWCU-V-1, and RWCU-V-4 (see pgs. 6-23, 6-24, and 6-32).
- 14. Delete any maximum isolation times listed for valves in section d.
Other Containment Isolation Valves of Table 3.6.3-1 in Technical Specification (replace with "NA"). These valves do not receive automatic isolation signals and the given stroke times do not represent stroke times required to meet containment isolation criteria as described in section 6.2.4 of the WNP-2 FSAR.
Individual justifications are as follows:
MSLC-V-3A, B, C, D Main steam leakage control isolation valves, these valves are normally closed. System is.
initiated after a LOCA, The valves auto-isolate on high leakage conditions.
RFW-V-65A, B Feedwater isolation valves, auto-isolation is not i desirable since the feedwater system is potentially a significant source of makeup. Feedwater check valves on either side of the containment provide
( immediate leak isolation, if required.
RWCU-V-40 RWCU vessel return isolation valve, can be manually closed upon indication that the RWCU pumps have tripped. The feedwater check valves provide immediate isolation.
HPCS-V-4, 15 These valves are the ECCS and drywell spray suction LPCS-V-1, 5 and discharge isolation valves. ECCS operation is RHR-V-16A, B essential during a LOCA; therefore there are no RHR-V-17A, B automatic isolation signals.
RHR-V-42A, 6, r.
RHR-V-4A, B, C !
HPCS-V-12 These valves are the RCIC and ECCS minimum flow LPCS-FCV-11 valves, they auto open on pump running and low flow. I RHR-FCV-64A, B, C They are shut at all other times. l RCIC-V-19 RCIC-V-68 The RCIC steam exhaust valve, normally open at all !
times. Should a leak occur, it would be detected and .
alarmed by the RCIC high temperature leak detection l circuit. '
RCIC-V-69 The RCIC vacuum pump discharge valve, normally open at all times. Can be remotely closed upon indication that vacuum can no longer be maintained in the baro-metric condenser.
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. RCIC-V-13 The RCIC injection valve, only open during systen operation. Injection line check valves on either
( side of containment provide immediate isolation, if required. Auto closes when the turbine throttle valve is closed following a turbine trip.
RCIC-V-31 The RCIC suppression pool suction valve, open only during system operation. Can be closed remotely by the operator on indication that the system is no longer operating.
RHR-V-73A, B RHR heat exchanger vent valves, normally closed.
Only opened for system vent and fill.
RHR-V-134A, B CAC to RHR drain valves, normally closed. Only opened during CAC operation.
CAC-V-2, 15, 11, 6, 4 CAC isolation valves, normally closed. System is CAC-FCV-1A, B, 2A, B only placed in operation if hydrogen is detected CAC-V-8, 13, 17 post-LOCA.
CAC-FCV-3A, B, 4A, B RRC-V-16A, B RRC seal injection isolation valves. Can be remotely tripped upon indication that the CRD or RRC pumps have tripped. The isolation check valves provide immediate isolation.
(
( CIA-V-20. Non ADS SRV and inboard MSIV supply isolation valve.
Can be remote manually closed on indication of low supply pressure. The isolation check valve provides immediate isolation.
CIA-V-30A, B ADS SRV supply isolation valves. Can be remote manually closed on indication of low supply pressure.
The isolation check valves provide immediate isolation.
CSP-V-5, 6, 9 The 4 second closing time limit results from a require-ment given in Branch Technical Position CSB 6-4, Containment Purging During Normal lant Operations ,
that purge system isolation valve closure times, incluoing instrumentation delays, should not exceed five seconds. However, these valves are butterfly vacuum breakers, not purga system isolation valves.
They only open when a vacuum exists in primary ;
containment. They are normally closed during purging operations.
- 15. Add FPC-V-149 to Table 3.6.3-1 of Technical Specification (pg. 6-22) per DCP 85-008-0A and 85-008-1C.
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Federal Register / Vol. 51. No.107 / Wednesday, luce 4,1986 / Notices 20381 No significant hazards consideration Paragraph 3. of Ucense Condition upgrades. and remove valves having no 4 comments received: No. 2.C.(16). safety related function.
LocalPubhc Room location: Swem Date ofInitialNoticein the Federal Dcte ofissuance: May 23,1986.
Ubraty, College of William and Mary, Register: Apn! 23.1986 (51 FR 15418). Effective Dode: May 23,1986. .
j Wilhamsburg. Virginia 23185. The Commission's related evaluation Amendment No. 27. -
Weshington Public Power Sapply of the amendment is contained in a Facility Opetuting License No. NPF-Syetom, Dockat No. 30497, WNP-2, S*I*tY. Evaluation dated May 23,1986. 21t Amendment revisea the Technical Richland Washiniton No significant hazards mnoideret'm Specifications.
cornmenta received: No. Date ofInitialNoticein the Federal Date ofopphcotionfor amendment: LecolPublic Document Room Register: April 23,1986 (51 FR 15416)
January 17,198E location: Richland Pubhc Ubrary, Swift ne Comminion's related evaluation Brief description of amendment:This and Northgate Streets. Richland, of the amendment is contained in a amendment will revise the WNP-2 Washington 99352. Safety Evolution dated May 23,1986.
Tec ca Sp c c o a 9, No significan b zards consideration I
, v i4 m Washington Public Power Supply System, Docket No. 50497. WNP-2, '
manual to outomatic. Valve FPQ-V-149 is the interface between the Suppression Richland, Washington *0] e DocumentRoom Pcol Cleanup System and the Fuel Pool Location: Richland Public Ubrary, Swift Dores of applicotmo for ornendmente and Northete Streets, Richland.
Coohng (FPC) System. At present it is I January 17,1986, and February 10, tee & Wa shingtorJ9352. I manually closed and locked durin8 Briefdescription of amendment: Thia normal power operation. ne change WasMagton WJeww SupW )
action amends the WNIL2 Technical will provide a motorized isolation valve Specification Table 3.6.3-1. Primary Syenem. Docket No. Ts0497. WNP-2, m the suppression pool cleanup return Containment isolation Valves" to: (1) a W>on
- hae and allow use of the FPC filter. Jteflect corrections and additiona to and Date of applicationfor amendment:
deminershzers for suppression pool deletions from the Excess Flow Check February 26.1966, as supplemented on deanup dunng reactor operations. Valve listings. Traversing Incore Probe April 7,24. 25,30 and May 22,1986.
Date ofissuance: May 13,1986. System valve listings, Residual Heat Effective Date:May 13.1986. Briefdescription of amendinent:This Removal System valve listings and action amends the WNP-2 Technical Amendment No. 24-Focihf) Opemting Ucense N. equipment qualification limits; (2) S ecifications to support the operation PF !. Amendment revised the reidentify certain valves in accordance ofWNP-2 at full rated power during the with current Supply System practines: next fuel cycle, Cycle 2. This reload (3) add valves previously omitted. (4) amendment changes the Technical t of/n al ' t n the Federal provide clarification to notes in the Specifications in the following areas:(1)
Redsler: March The Commission's 12.1986 related table:8503)'on evaluati (51 FR (5) correct typographical errors; Establishes operating limits for all fuel of the amendment is contained in a and (t) delete maximum isolation time types for the upcoming Cycle 2 Safety Evaluation dated May 13,1966. hstings for valves not performing an operation;(2) reflects the replacement of No significant hazards consideret'on automatic containment isolation 128 initial core fuel assembhes with comroents received- No. function. Exxon Nuclear Company (ENC) fuel LocalPublic Room Location Richland Date ofissuance: May 23,1986. assemblies for the upcoming Cycle 2 Public Ut ary, Swtit and Northgate Effective Dota: May 23,1986. operation: and (3) modifws the Bases Strr e s. Richland. Washingten 99352. Amendment No. 26. section of the Technical SpectBcation to Facility Operating License No. NPF. account for the use of Exxon fuel W ddagton Public Pownr Supply 21: Amendment resises the Technical assemblies.
Lyt tem, Docket No. 544r17, WNP-2, Specifications. . Date ofleeuance: May 23,1986.
Richland, Washington Effectire Deter May 23,1986.
Date ofInitialNotim in the Federal Dates o/opphcobon for amendment: Register: April 23,1986 (51 FR 15416). Amendment No. 28.
March 28.1986, as supplemented May 7 The Commission's related evaluation Focility Operating License No. NPT-and 8.1966. of the amendment is contained in a 21: Amendment revises the TechrJeal Brief description of amendment: This Safety Evalustion dated May 23.1986. Specifications.
action amends a hcense condition of the No significant hazards consideration Date of /nitialNoticein the Federal WNP-2 Operating Ucense NPF-21. comments received: No. Register: April 23,1986 (51 FR 1M17)
Attachment 2. Paragrsph 3.(a) of Ucense loco /Pubhc Document Room The Commission's related evaluation Condition 2.C.(16) now requires that the Location: Richard Public 1.ibrary. Swift of the amendment is contained in a licensee shall implement (install or and Northgate Streets, Richland, ' Safety Evalution dated May 23,1986.
upgrade) requirements of Regulatory Washington 99352. No significant hazards consideration Guide 1.97, Rev. 2, with the exception Weehington Public Power Bugply conents red h only of flux monitoring. prior to startup Zom/ Public Document Room Dok W-2, following the first reh:elmg outase.This amendment permits implementation of
[,'a w,, ,
locotton Richland Public Ubrary, Swift and Northgate Streeta, Richland, this Regulatory Guide requirement to be Date 0/ Application forannendment Washington 9s352.
delayed for the Suppression Poollevel January 17,1986.
Monitoring System until etartup Briefdescription of amendment This M El e c Dock 50-2s, Yanka Intlowing the second refueling outage. action will amend the WNN2 Technical Date oflssuance:May 23,1966. Specificat>ons by changing TaAnw=1 Power Station, F=nktin County' Effecve Date: May 23,1986. Specification Table 3.4.4.S-1 Motor Maesacliuseus Amendment No. 25. Operated Valves Thermal Overload Date of application for amendment:
Facihty Operating License No. NPF- Protection" to ed.] valves previously May 26,1981, as revised January 23,1984 2t: Amendment revises Attachment 2, o.nitted, add valves as a roeult of system and February 26,1965.
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l 15410 Federal Register / Vol. 51, No. 78 / Wednesday. April 23, 1986 / Notices maximum isolation time listings for application does not involve a Thelicensee has determined and the staff agrees, that the requested valvs not performing an automatic I significant hazards consideration.
Loro/ Public Document Room amendment does not:(1) Involve a containment isolation function.
locolion: Swem tabrary College of significant increase in the probability or Table 3.6.3-t is provided to list William and N1ary. Williamsburg, consequences of an accident previously containment isolation valves and to Virginia 23183. evaluated because the proposed *nsure operability of these valves so ,
Attorney for licensee: Mr. hiichael W. changes and additions to the list do not that the containment atmosphere can be j htaupin, ilunton and Williams. Post deviate from the existing overinad isolated from the outside environment in Office Dov 1535. Richmond, Virginia design criteria and the removal of non- the event of a telease of radioactive 23213. safety related valves from the list has no material to the containment. Section (a)
NRC Project Director lxster S. affect on the probability or of the table provides those valves and Rubenstein. consequences of a previously evaluated maximum isolation time limits allowed addident: or (2) create the possibility of so that on an automatic isolation Washington Public Power Supply a new or different kind of accident from demand. the containment will be System. Docket No. 50-397. WNP-2, an accident previously evaluated isolated from the outside environment j Richland. Washington because the overload design criteria consistent with the assumptions used in base not been changed, the additioni the Final Safety Analysis Report Design Date of amendment request: January 1 M 966. have adhered to the criteria and the Base Accident 1,0CA analyses. 4 Description of ome'ndment request: deletion of non safety related valves Basis forno significant hazards This preposed amendment,if approved. does not introduce a new or different consideration determination:The will modify the WNP-2 Technical kind of accident: or (3) involve a Commission has provided standards for Specifications by changing Te; hnical significant reduction in a margin of determining whether a significant Specification Tabte 3.8.4.3-1. Motor safety because as discussed in (1) the hazards consideration exists (10 CFR I Operated Valves Thermal Overload added valves conform to the overload 50.92(c)). A proposed amendment to an I Protection
- to add valves previously design criteria and hence do not operating license for a facility involves l omitted, add vah es as as result of challenge a safety margin and the no signif'icant hazards consideration if {
sy stem upgrades, and remove valves removal of non-safety related vahes can operation of the facility in accordance haying no safety related function. not impact a safety margin. with the proposed amendment would
'I he vah es previously omitted from Based on our review of the proposed 8" 7 "
the Technical Specifications Table were modification, the staff finds that there h'fp ygr 0n ences of a madsertently left out of the original exists reasonable assurance that this accident previousiy evaIuated: or (z) table when the Technical Specifications proposed change will have little or no mate &a possWy of a new or were created prior to licensing. The impact on the public health and safety. M en nt nd of accent kom an valves being added resulted from the Accordingly, the Commission proposes accident previously evaluated; or [3]
fuel pool cooling modifications that to determine that the proposed change inv Ive a sign & ant redudon M a were committed to prior to licensing and to the WNP-2 Technical Specifications m rgin f safety.
were recently effected.The valves beinS involves no significant hazards The licensee has determined, and the removed from the table were incorrectly considerations. staff agrees, that the requested inserted when the Table was created as Loco / Public Document Room:
they are not used in any safety related Richland Public Library. Swif t and emendment does not:(1) Involve 3 significant increase in the probabdity or system. Northgate Streets. Richland, conseques of an accident previously Basis for no significant hazards Washington 99352. evaluated because the proposed l consideration determination:The Attorney for the Licensee: Nicholas Commission has provided standards for Reynolds. Esquire. Bishop. Liberman, isolation time deletions do not affect the determining whether a significant Cook. Purcell and Reynolets.1200 response of the plant to a primary hazards consideration exists (10 CFR Seventeenth Street NW, Washington. containment isolation demand and tne 50 92(c)). A proposed amendment to an remainder of the changes merely DC 20036.
operating license for a facility involves NRC Project Director: E. Adensam. provide corrections to listings in the no significant hazards consideration if table that were previously evaluated in Wash,mgton Public Power Supply the Final Safety Analysis Report; or (2) operation of the facility in accordance l System, Docket No. 50-397, WNP-2. create the possibility of a new or !
with the proposed amendment would Richland Washmgtoe different kind of accident from an net:(1) Involve a significant increase in the probability or consequences of an Dates of Amendment Request: accident previously es aluated because accident previously evaluated or (2) January 17.1906 and February 18.1986. the changes are corrections and create the possibility of a new or Description of Amendment Request therefore can not introduce new or different kind of accident from an This proposed amendent. if approved, different accident scenarios and the accident previously evaluated; or (3) will modify the WNP-2 Technical deletion of isolation times for valves not involve a significant reduction in a Specification Table 3.6.3-1. " Primary required to isolate automatically does margin of safety. Containment Isolation Valves" to not alter systems or con litions The licensee has determined, and the reflect:(1) Corrections and additions to previously evaluated; or (3) involve a staff agrees, that the requested the Excess Flow Check Valve listings, significant reduction in a margin of amendment does not:(1) Involve a Traversing Incore Probe System valve safety because no safety related significant increase in the probability or listings, and equipmeht quahfication functions (limits for containment consequences of an accident previously limits: (2) reidentify certain valves in isolation) will be changed as a result of evaluated; or (2) create the possibility of accordance with current Supply System this proposed amendment, a new or different kind of accident from practices (3) add valves previously Based on our review of the proposed and accident previously evaluated; or (3) omitted: (4) provide clarification to modification, the staff finds that there involve a significant reduction in a notes in the table;(5) correct exists reasonable assurance that this margin of safety. typographical errors; and (6) delete proposed change will have little or no
t Federal Register / Vol. 31 No. 78 / Wednesday, April 23, 1986 / Not!ces 15417 impact on the public health and safety. reload is very similar to Example (iii) except for the center region and the core Accordingly, the Commission proposes provided by the Commission (48 Federal periphery. Changing from a zone core to determine that the requested change Register 14870. April 0.1983) of the types loading pattern uspd during the first fuel to the WNp-2 Technical Specifications of amendments not likely to involve cycle to a scatter loading pattern for the ins olves no significant hazards significant hazards considerations. new reload assemblies durmg the considerations. Example (iii)is an amendment to reflect second cycle is an accepted reload Loca/ Public Document Room; a core reload where: method that has been approved by ine Richland Public Library. Swift and (1) No fuel assembles significantly NRC staff for other DWR plant reloads.
l Northgate Streets. Richland. different from those found previously Thus this core reload involves the use Washington 99352. acceptable to the Commission for a of fuel assemblies that are not Attorney for the Licensect Nicholas previous core at the facility in onaalinn significantly different from those found Reynolds. Esquire. Bishop. Liberman, are involved: previously acceptable to the Cook. Purcell and Reynolds.1200 (2) No significant changes are made to Commission for a previous core at this Seventeenth Street NW., Washington. the acceptance criteria for the Technical facility. The proposed amendment DC 20030. Specifications: would change the Technical NRCProject Director E. Adensam (3)The analytical methods used to ;pecificatinns to reflect new operating demonstrate conformance with the limits associated with the fuel to ba Washm, gton Public Power Supply S> stem. Docket NJ. 50-397, % NP .,. Technical Specifications and regulations inserted into the core based on the new are not signif;cantly changed; and core physics and are within the Richland Mashmgton (4) The NRC has pr'viously found acceptance criteria. In the analyses Date of amendment request: February such methods acceptable.
supporting this reload. there have been 26,1986. This reload will consist of 764 no significant chang % in acceptance Description of omendment request: assemblies. app'oximately r 632 of which criteria for the Technical Specification The prorosed amendment would revise are once burned GE fuel assemblies and approximately 132 of which are new and those analvtical methods used have the WNP-2 Technical Specifications pieviously been found acceptable by the (TSI to support the operation of WNP-2 ENC. Type XN-1 fuel assembhes. T he NRC.
at full rated power during the upcoming Exxon fuel assemblies are very similar to the GE fuel assembhes except for The only ditterence between this Cycle 2. The proposed amendment slight differences in the mechanical. reload and Example (iii) provided by the request to support this reload changes thermal. hydraulic and nuclear design NRC is related to the use of the Exxon the Technical Specifications in the nalytical methods v.hich are slightly following areas: (1) Establishes Al,though the Exxon f elis very 8i ar to i e GE e tesg different from th.> CE methods used for operating limits for all fuel types for the Cycle t es noted above.The Exxon upcommg Cycle 2 operation: (2) reflects d e g hydraulic and nuclear design of the analytical results are not significantly
- he replacment of approximately > 132 different from those previously found imtial core fuel assembhes with Exxon bundles. and the use of different accepiaWe to the NRC for the initial Nuclear Company (ENC) fuel assemblies analysis methodologies. required that a wide range of reanalyses be performed core at WNP-2 and the methods for the upcoming Cycle 2 operation
- and previously have been approved by the (3) modifies the Bases section of the by Exxon. These reanalyses included reanalyzing for anticipated operational NRC staff for use in other BWR's.
Technical Specification to account for occurrences. performing LOCA and in addition to 1he similarity between the use of Exxon fuel assemblies the proposed amenament and the To support the license amendment MAPLiiGR analyses for the Exxon fuel and' analyzing for the rapid drop of a Con' mission's Example (iii), the request for operation of % NP-2 during Commission has prosided standaras f or Cycle,2. the Supply System submitted as high worth control rod to assure that determining shether a significant attachments to the application the excessive energy will not be deposited following: in the fuel. Analyser for normal hazards consideration exists (10 CFR operation of the reactor consisted of fuel 59.92(c)). A proposed amendment to an I. WNP-2 Cycle 2 Reload Summary operating license for a facihty involves evaluations in the areas of mechanical.
Report (WPPSS-EANF-101) thermal. hydraulic and nuclear design. no significant hazards consideration if includes the Startup Physics The use of the ENC type XN-1 fuel operation of the facility in accordance Program assemblies and the associated with the proposed amendment would
- 11. WNP-2 Cycle 2 Reload Analysis analytical methods used for the Cycle 2 not:(1)Invoh e a significant increase in (XN-NF-86-01. Rev 1) reload analyses have been previously the probability or consequences of an 111. WNP-2 Cycle 2 Plant Transient approved by the NRC Staff for use in accident previously evaluated, or [2)
Analysis (XN-NF-85-143. Rev 1) other boiling water reactors (BWR's). create the possibility of a new or IV. WNP-2 LOCA-ECCS Analysis Based on these prior reviews, the NRC different kind of accident from an MAPLiiCR Results (XN-NF-85-139) staff has determined that there are only accident presiously evaluated; or (3)
V Technical Specification Changes small differences between the use of ins oh e a significant reduction in a During the first refueling outage Exxon and GE analytical methods. margin of safety.
approximately 132 General Electric (GE) Another difference between Cycle 1 On the basis of esaluation performed initial fuel assemblies (approximately core and the Cycle 2 core reload is the in accordance with to CFR 50.92. and one fifth of the core) will be replaced core loading pattern. Cycle 1 is a the fact that the analytical methods used with new but substantially similar standard GE BWR/5 initial core hus e been approved previously by the Exxon. Type XN-1 (8 x 8 bundles. 2.72 configuration consistir.g of fuel NRC staff und do not provide results (weight) percent enrichment). fuel assemblies of similar enrichments significantly different, the Supply a s.e emblies. placed in a specific zone within the core. System has concluded, and the staff Basis forproposed vo significant in constrast the Cycle 2 core will be agrees, that operation of WNP-2 in hazards consideration determination based on the conventional scatter load accordance with the proposed reload The proposed amendment to the WNP-2 principle where fresh reload assemblies amendment would not:(1) Involve a Technical Specifications to support this are scatter loaded throughout the core significant increase in the probabihty or
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, Routing Slip TRANSMITTAL 0F DIVISION OF BWR LICENSING WORK REQUEST SPECIAL NG - PROCESS WITHOUT DELAY TAC #-Plant Name-T tie 409S3 NP 2. Adedef /hile 3. 4. s-t /?n m Q ,,.f,, 4
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B. Will the review benefit from regional prox 1mity to the site? YES / d@
C. If the answer to A and/or B is "yes", explain why the review is not being sent to the Regions.
SEQUENCE NAME DATE i
- 1. Project Manager /DA 6-d&gs
- 2. Project Director Adc,f.sa ,, g W 0$ 1986 T/r This action is requested to be added to the review branch's current comitments This action is requested to be completed in lieu of TAC #
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- 4. Regional Div. Director / Asst.
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This action is accepted for completion with a target date of in lieu of completing TAC # in this fiscal year
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