ML19316A929

Forwards Tech Spec Pages 204A & 205 for Addition & Substitution,Respectively,For Amend 41 to License DPR-35

ML19316A929
Person / Time
Site:	Pilgrim
Issue date:	04/28/1980
From:	Ippolito T Office of Nuclear Reactor Regulation
To:	Andognini G BOSTON EDISON CO.
References
NUDOCS 8005280069
Download: ML19316A929 (4)

Text

{{#Wiki_filter:-. _ 4 +# 0,, UNITED STATES NUCLEAR REGULATORY COMMISSION c y WASHINGTON, D. C. 20555 April 28, 1980 Docket No. 50-293 Mr. G. Carl Andognini Boston Edison Company M/C NUCLEAR 800 Boylston Street ~ j Boston, Massachusetts 02199

Dear Mr. Andognini:

By letter dated February 22, 1980, we transmitted Amendment No. 41 to Facility Operating License No. DPR-35 for the Pilgrim Nuclear Power Station relating to Multiple Control Rod Removal during Refueling Operations. Certain Technical Specification pages necessary for implementation of Amendment No. 41 were inadvertently omitted. Please add the enclosed 204A and substitute the enclosed page 205 for the one issued with Amer dment No. 41. Sincerely, Thoma A. Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors

Enclosure:

T. S. pages 204A and 205 cc w/ encl: See next page r THIS DOCUMENT CONTAINS POOR QUAUTY PAGES Boos 2s0069 ?

Mr. G. Carl Andognini Boston Edison Company April 28,1980 cc: Mr. Paul J. McGuire U. S. Environmental Protection Pilgrim Station Acting Manager Agency Boston Edison Company - Region I Office RFD #1, Rocky Hill Road ATTN: EIS COORDINATOR Plymouth, Massachusetts 02360 JFK Federal Building Boston, Massachusetts 02203 Energy Facilities Siting Council 14th Floor,- One Asburton Place,. Boston,-Massachusetts 02108 Henry Herrmann, Esquire Massachusetts Wildlife Federation 151 Tremont Street i Boston, Massachusetts 02111 Plymouth Public Library North Street Plymouth, Massachusetts 02360 Massachusetts Department of Public Health ATTN: Commissioner of Public Health 600 Washington Street Boston, Massachusetts 02111 Water Quality & Environmental Commissioner Department of Environmental Quality Engineering 100 Cambridge Street Boston, Massachusetts 02202 Mr. David F. Tarantino Chainnan, board of Selectmen 11 Lincoln Street { Plymouth, Massachusetts 02360 Director Technical Assessment Division Office of Radiation Programs (AW 459) i US EPA Crystal Mall #2 Arlington, Virginia 20460

3.10 BASES 3. Core Monitoring ne SRM's are provided to cocitor the core during periods of station shutdown during refueling operations and sca:1on s:ar:up. and to guide the opera:c: Requ'b:ng two cperable 57d's in or adjacent to any core quadrant whe -i or ce n e require:ent of 3 counts per second provides du d :g such altera icas, ass rance that neutron flux is being menitored and insures that startup is conducted only if the scurce range flux level is above the mini =u= assuced in the cen:rol red drop tecident. "t %" I conditions for operation of the SRu. subsys:e= of the Neutren h e ' i""4 oni:oring Sys:em are derived #.c 65.e Station Nuclear Safety Operational w calysis (Appendix G) and a functional analysis of the neutt:n co,:or.,ng ne specification is based on the Operational Nuclear Sa:ety Re-systen. quire =ents in subsectics 7.5.10 of the Saf ety Analysis Repor. cells (four A spiral unloading pattern is one by which the fuel in :he oute:=ost fuel bundles surrounding a centrol blade) is removed first. Unicad ng continues e=oving the remainics ouse es: fuel cell by cell. De center cell vill be by d :las-e=oved. Spiral leading is :he reverse of unloading. Spiral unloac,_ng e a.d releading vill preclude the crez:ic of flux traps (=ederator filled cavi:1es surrounded on all sides by fuel). pu'.in-spiral unloading, the 57.M's shall have a= ini:121 count rate of 13 epsD I'5especialcondi: ods fully inserted. ..< g 1o= of eceplete spiral core unicading, it is expected h$ derthe count rate of :he 573.'s vill d:cp belov 3 cps before all o. the.uel.s tha t a ever ne=ber of ceunts vill not unicaded. a dd _,,-, c 5 1 Sidee :u..ere V,3, be e e2e eity , u e _3 storage -"c,uel has bee .e -ye to :he scen: s be opera:icnal s -r esen-a haza::. ane. *- e-the SFF.'s vill :o longer be recu, red;, ec,., S the SRM s toc,e able and can be re n

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3.10 BASES 1

• . Multiole Centrol ?.ed Ie,3 val' tese specifica:1c s e:sure tha: =ainte:acce er repair of co::::1 rods or : d drives vill be perser:ed under co:di:ie:s tha: 11 i: :he probability of inadvertent

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+ insures tha: vi:hdrawal cf asether cc::rol ::d does =c: result 1: 1:adver:e:: cri:icali:7 Each con:rol rod esse::ially prevides reac:1vi:y c::::al fe the fuel asse=blies 1: :he cell associated vi:h the cc:::el red. Thus, re=ovel of at entire ce.1 (fuel asse=blies plus ect:rel red) rescits in a 1cver reac:1ti:y pe:e::ial of th.e cc:E. I. 10 3> SIS l A. Refuelist Interlocks l 1 l Cc=plete func fecal testi=g of all refueli=g i=:erlocks before any refueling eu: age vill p;cride pesi:ive indicatie -34: :he i=:erlecks opera:e 1: the + j si:ustic:s for which they were desig=ed. 37 leadi=g each beis: vi:b a weigh: equ:1 to the fuel asse:bly, positic:ing the refueling platf :=, a:d vi:h-I draving cent :1 rods, the in:erlocks c.a= be subjected :o valid cpera:1 :a1 tests. Waere redunda:cy is provided 1: the logic circuitry, :es:s ca be perfor=ed to assure tha: each redu: dan: legi: ele en: ca: indepe=dently peric = i:s fu.seticus. i k I. Core Me itorier p2;uiri=g the 57M's :o be fu==:1e: ally :ested prier :c t.ny core al:ers:1:: i assures :ha: the S7Z's vill be cperable a: :he s:ar: ef that alteratic:. Se daily respense che:k of the STd.'s e:sures : heir centi =ued cperabili:7 3 i 1 4 I 1 i 4 4 l .....l L 2. ~ EI

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