BECO-84-075, Forwards Corrected App a Index & Addl Tech Spec Pages Re Fire Protection Improperly Identified in 840327 Change Request

Forwards Corrected App a Index & Addl Tech Spec Pages Re Fire Protection Improperly Identified in 840327 Change Request

ML20197G743
Person / Time
Site:	Pilgrim
Issue date:	06/11/1984
From:	Harrington W BOSTON EDISON CO.
To:	Vassallo D Office of Nuclear Reactor Regulation
References
BECO-84-075, BECO-84-75, NUDOCS 8406180140
Download: ML20197G743 (5)

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,. . ..e BOSTON EDISON COMPANY 800 BDYLETON STREET BOSTON, MAsSACHUBETTs 02199 WILLIAM D. HARRlNGTON C'.IT" ""'"" June 11, 1984 BECo 84-075 Mr. Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 License No. DPR-35 Docket No. 50-293 Supplement to Proposed Fire Protection Technical Specifications

Dear Sir:

On March 27,1984 (BECo 84-047), Technical Specifi cation changes concerning fire protection were submitted for your review and approval.

Inadvertantly, some of the pages of t' x A index were improperly identified in conformance i .iusion of addi-ional pages forwarded with the subM' .. r'our (4) pages in the following section were not ' ,part of the change request submittal.

Enclosed please find a properly-1dentified index and the addi-tional pages identified in the index and remarked accordingly.

Please replace the previously-submitted index with the enclosed reidentified index and additional pages.

I We have notified our Project Manager, Paul H. Leech of our prior omission, and he is awaiting receipt of this corrective package.

Very truly yours, C

ERM:pjd Enclosures

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• Surveillence Page No.

3.7 CONTAINMENT SYSTDiS 4.7 152 A. Primary Containment A 152 B 158 e B. , Standby Gas Treatment System C. : Secondary Containment C 159 Primsry Containment Isolation Valves D 160 D.

'3.8 RADIOACTIVE MATERIALS 4.8 177

, s ,

A 177

'O A.' Liquid Effluents B 179 U-['

B. VAirborne Effluents '

C. (Deleted) 182 Environmental Monitoring Program D D.

Mechanical Vacuum Pump E 184 E.

3.9 AUXILIARY ELECTRICAL SYSTEMS 4.9 194 Auxiliary Electrical Equipment A 194 d A.

Operation with Inoperable Equipment B 195 x B.

4.10 202 3.10 CORE ALTERATIONS 202

.'\ A. Refueling Interlocks- A Core Monitoring B 202

/. ,

B.

C 203 Q C. Spent Fuel Pool k*ater Level MT 3.11 a,

REACIOR FUEL ASSEMBLY 4.11 205A A. Ave' rage Planar _ Linear Heat A 205A

-9 Generation Rate (APLHGR) 205A-1 Linear Heat Generation Rate (LEGR) B

' da B.

C 205E

?) C. Minimu= Critical Power Ratio" (MCPR) tij 206

-3.12 FIRE PROTECTION ,

4.12 A. Fire Detectio'n' Instrumentation A 206 B. Fire Water Supply System B 206a C. Spray and/or Sprinkler Systems C 206c D. Fire Hose Stations D 206d E. Gaseous Suppression System E 206e F. Fire Barrier System F 206f C. Alternate Shutdown Panels G 206g I'.

, t 206o

. 4.0, MISCELLANEOUS RADIOACTIVF, MATERIALS SOURCES 2060 >

I,>  ! .

4'.1 Sealed Scurce Contamination 2060 t

4.2 Surveillance Requirements 206p

,', ,4. 3~ Reports 206P 4.4 hecords Retention Amendment No.

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ii

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s 4 - - . - -

l Pr-ge Nay  ;

5.0 HAJOR DESIGN FEATURES 206q r

5.1 Site Features 206q l 5.2 Reactor 206q 5.3 Reactor Vessel 206q 5.4 containment 206q j 5.5 Fuel Storage 207 5.6 Seismic Design 207  ;

208  ;

6.0 ADMINISTRATIVE CONTROLS I 208  !

6.1 Responsibility 6.2 Organization 208 i 6.3 Facility Staff Qualifications 208 20Ba 6.4 Training 212 L 6.5 Review and Audit 216 6.6 Reportable Occurrence Action 216  :

6.7 Safety Limit Violation '

216 6.8 Procedures 217  !

6.9 Reporting Requirements 224 i

• 6.10 Record Retention 226 6.11 Radiation Protecticn Program i 6.12 (Deleted) 226 6.13 High Radiation Area 227 6.14 Fire Protection Program 7 228 6.15 Environnental Qualification l

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l l Amendnent No. iii l

4.0 MISCELLANEOUS RADIOACTIVE MATERIALS SOURCES 4.1 SEALED SOURCE CONTAMINATION Each sealed source contcining radioactive material either in excess of 100 microcuries of beta and/or ga=ma emitting material or 5 microcuries of alpha emitting material shall be free of 2',0.005 microcuries of removable contamination at all ti=es.

Each sealed source with removable contamination in excess of the above limit shall be immediately withdrawn from use and:

a. Either decontaminated and repaired, or

b. Disposed of in accordance with Ce: mission Regulations.

l 4.2 SURVEILLANCE REQUIREMEhTS

a. Test Recuirements - Each sealed source shall be tested for leakage and/or conta=ination by:

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(1) The licensee, or (2) Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.

b. Test Frecuencies - Each category of sealed sources, excluding startup sources and fission detectors previously subjected to core flux, shall be tested at-the frequency described below.

(1) Sources in use - At least once per six months for all sealed sources containing radioactive material:

(a) With a half-life greater than 30 days, excluding Hydrogen 3, and (b) In any form other.than gas.

(2) Stored sources not in use - Each sealed source and fission detector shall be tested prict to use or transfer to another licensee unless tested within the previous six months. Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed into use.

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2060 Jutenchnent No.

(3) Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.

4.3 REPORTS A report shall be prepared and submitted to the Com=ission on an annual basis if sealed source or fission detector leakage tests reveal the presence of 3 0.005 microcuries of removable contamination.

4.4 RECORDS RETEhTION A complete inventory of radioactive materials in possession shall be maintained current at all times.

Records required to be maintained for two years:

a. Test results, in units of microcuries, for leak tests performed pursuant to Specification 4.2.

b. Record of cnnual physical inventory verifying accountability of sources on record.

BASES SEALED SOURCE CONTAMINATION The limitations on sealed sourced removable contamination ensure that the body or individual organ irradiation does not exceed allowable limits in the '

event of ingestion or inhalation of the source material. The limitation on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.

Quantities of interest to this specification which are exempt from the leakage _ testing are consistent with the criteria of 10 CFR Part 30.11-20 and 70.19. Leakage from sources excluded from the requirements of this

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specification is not likely.to represent more than one maximum per=1ssible body burden for total body irradiation if the source material is inhaled or ingested.

206p Amendment No.

v.AJOR DES!GN FEATURES 5.1 SITE FEATURIS_

Pilgri:n Nuclear Power Station is located on the Western Shore of Cape Cod Bay in the Town of Flymouth, Plymouth County, Massachu-sects. The site is located at approxi=ately 4151' north latitude and 700 35' vest longitude on the Manonet Quadrangle, Massachusetts, Plymouth County 7.5 Minute Series (topographie) =ap issued by U.S.

Geological Survey.

• UIM coordinates are 19-46446N-36922.

The reactor (center line) is located approximately 1800 feet from the nearest property boundary.

5.2 RRACTOR A. The core shall consist of not more than 580 fuel asse=blies of 8x8 (63 fuel rods) and pbx 8R (62 fuel rods).

3. The reactor core shall contain 145 cruciform-shaped control rods. The control material shall be boron carbida pavder (B4 C) compacted to approximately 70% of theoretical density.

5.3 REACTOR VESSEI, The reactor vessel shall be as described in Table 4.2.2 of the FSAR.

The applicable design codes shall be as described in Table 4.2.1 of the FSAR.

5.4 CON AIhv..ENT A. The principal design paraneters for the pri=ary contain=ent shall be as given in Table 5.2.1 of the FSAR. The applicable design codes shall be as described in Section 12.2.2.8 of the FSAR.

! 3. The secondary containment shall be as described in Section 5.J.2 of the FSAR.

C. Penetrations to the pr:'. mary contai= ment and pipi=g passing through such penetrations shall be designed in accordance with standards set forth in Section 5.2.3.4 of the FSAR.

A=end ent No. 2069 m