ML20148G782

Submits Proposed Change 150,Suppl 1 to Tech Specs,Revising Tech Specs to Be Consistent W/Revised Model STS for Fire Protection

ML20148G782
Person / Time
Site:	Yankee Rowe
Issue date:	07/18/1977
From:	Johnson W YANKEE ATOMIC ELECTRIC CO.
To:	Office of Nuclear Reactor Regulation
References
WYR-77-69, NUDOCS 8011130362
Download: ML20148G782 (26)

Text

- ' ,

Droposed Change No. 150 ~l

, , , I (...jpplement No. 1

. Telephone 617 366-9011 Tirx 710 390 0739 YANKEE ATOMIC ELECTRIC COMPANY urR 77-69

.1 .

20 Turnpike Road Westborough, Massochusern 01581

.YAN KEE w A

% -e ...

ghdg( M July 18, 1977 -

O QS&W United States Nuclear Regulatory Commission

1. f Washington, D. C. 20555' veh .

/

Attention: Office of Nuclear Reactor Regulatica $ b

Reference:

(1) License No. DPR-3 (Docket No. 50-29)

(2) USNRC letter to R. H. Groce from A. Schwencer, dated 12/1/76,

Subject:

Technical Specificacions for Fire Protection Systems (3) Supplement to letter described in Reference (2)

USNRC to R. Groce dated 12/8/76 (4) YAEC letter from J.L. French to USNRC dated 1/31/77 in response to Reference (2)

(5) YAEC letter from D.E. Vandenburgh to USNRC dated 3/18/77,

Subject:

Technical Specifications for Fire Protection Systems (Proposed Change No.150)

(6) USNRC letter to R.H. Groce from A. Schwencer, dated June 17, 1977, Subj ect : Revised Model Technical Specifications for Fire Protection Systems Subj ect : Fire Protection

Dear Sir:

Pursuant to Section 50.59 of the Commission's rules and regulations, and in accordance with Reference (6), Yankee Atomic Electric Company hereby requests the following changes to the Technical Specifications:

PROPOSED CHANGE: Reference is made to Appendix A of Operating License No.

DPR-3 issued to the Yankee Atomic Electric Company for the Yankee Powe Plant. We propose to modify the Technical Specifications as follous:

Reference (5) provided Technical Specifications for Fire Protection Systems for the Yankee Rowe Plant. Sased on your letter of June 17, 1977, (Ref erence (6)) we are now revising our ref erenced submittal to be consistent with the revised model Standard Technical Specifications fcc Fire Protection.

These specifications are presented c.s Attachment "B" to this letter.

Deviations from the approved Model Standard Technical Specifications are presented as Attachment "A".

THIS DOCUMENT CONTAINS ,.

P00R QUAJTY PAGES

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8011180 38Q J

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United States Nucleag Regulatory Commission July 18, 1977 Attn: Office of Nuclear Reactor Regulation Page Two REASON FOR CHANGE: The purpose of this change is to incorporate into the Yankee Rowe Technical Specifications those changes requested in References (2), (3) and (6).

SAFETY CONSIDER?sTIONS: The addition of Tecnnical Specifications which relate to fire protection systems e,nd which are being submi:ted in response to an h1C request do not endanger the hecith and safety of the public. This Proposed Change has been reviewed by the Nuclear Safety Audit and Review Committee.

SCHEDULE 07 CHANGE: These changes to Yankee Rowe Technical Specifications will be made immediately upon Comm1nsion approval.

Respectfully submitted, YANKEE ATOMIC ELECTRIC COMPANY

, 11 & W W. P. Johnson Vice Presider.t COMMONWEALTH OF MASSACHUSETTS)

)ss.

COUNTY OF WORCESTER )

Then personally appeared before me, W. P. Johnson, who being duly sworn, did state that he is Vice President of Yankee Atomic Electric Company and that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Yankee Atomic Electric Company, and that the statements thercin are true to the best of his knowledge and belief.

aR, .

Armand R. Soucy Notary Public My Commission Expires September 9, 1977

l Attachment A Justificatio'n for Departure from'the Mcdel Technical Specifications for Fire Protection System Y-R Tech. Spec.  : clel Teen. Spec, Dcparture/ Justification Del' tic, L.3.2.9.2 Yankee Rows has no NFPA Code 72D Class A supervised circuits.

Deletion 3.7.1.1.b The Yankee Rowe fire suppression water system incorporates a single water source (Sherman Pond) versus l sepcrate water supplies.

4.7.10.1.b 4.7.11.1.b The fire pumps at Y.R. contain no recirculation feature.

4.7.10.1.c 4.7.11.1.c There are no testable automatic valves required to operate during actuation of the fire suppression water system at Y.R.

4. 7 .10.1. d 4.7.li.1.d A semiannual flush is not required by local water conditions.

4.7.10.1.e 4.7.11.1.f System flow testing and flushing is performed en a refueling interval basis.

3.7.10.2 3.7.11.2 The requirement for a continuous fire watch ACTION level a. ACTION level a. has been replaced with establishment ,f a roving patrol to check the af f ected crc 2(s) hourly. The Y.R. water spray system is not automatically initiated. Therefore, even with the system inoperable, no automatic protection has been lost. Provision of

. backup equipment, as required by other parts of this spec., is sufficient to restore the level of protection to basic-a)1y what it was prior to the failure.

Deletion 4.7.11.2.b.1 The water spray system at Y.R. is a manually acf.uated system and as such includes no automatic valves.

3.7.10.3 3.7.11.3 The requirement for a continuous fire watch ACTION Icvel a. ACT70N 1cvel a. has been replaced with establishment of a roving patrol to check the affected area (s) hourly. The Y.R. C09 system is not auto-catically initiated.' Therefore, even with the system inoperable, no automatic protection has been lost. Provision of backup equipment, as required by other parts of this spec., is cufficient to restore the level of protection to basically what it was prior to the failure.

(

• 4 Y-R Tech. Socc. ,

Modal T::5. Spec. Denarture/Justift:atien ,

4.7.10.3.a 4.7.11.3.a The CO2 cylinders at Y.R. are checkad by verificaticn of the contained wcipht of CO,. This surveillance is performed e.t fefueling intcrval basis i.e.

18 mon:hs.

Deletier 3.7.11.4 Yankee Rowe has no llalon system.

Deletion 4.7.11.4 Same as 3.7.11.4 above.

3.7.11 3.7.12 The requireacnt for a continuous fire watch ACTION level a. has been replaced with establishment of a roving patrol to check the affected arca(s) hourly. The reduction of fire protection capabilities inherent in a non-functional penetration barrier is not sufficient to warrant a continuous fire watch. The provision of a roving patrol is consistent with other requirements of this specification.

I"CEX

4. DEFINITIONS 1

PAG- ,

p5ECliG_n-- t

)., ._........ .  ;

P

sfin d T rr3 . . . . . . . . . . . . . ........................t...... 1-1  !,

f Thermal Pc.:er ............................................ 1-1 l

Rated Thermal Fower ...................................... 1-1 Operational Hede ......................................... 1-1 Action ................................................... 1-1 l Crarchie - 0;sr:bility ................................... 1-1 1

Re portabl e Oc currenc e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 Containment Integrity .................................... 1-2 l r

l Chan n el Cal i bra t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 i P

Channel Check ............................................ 1-2 l Channel Functional Test .................................. 1-3 l Core A'.teration .......................................... 1-3 l Snutdown Margin .......................................... 1-3 s 1

Identified Leakage ....................................... 1-3 l; i

Un i d en ti fi ed L ea ka g e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 j Pressure Boundary Leakage ................................ 1-4  !,

i Ca s e Equi val e nt I-131 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4  ;

1 '

Staggered Test Basis ..................................... 1-4 j l

l Frequency Notation ....................................... 1-4 t

Physics Tests ............................................ 1-4 l t

E-Average Disintegration Energy .......................... 1-4 Ei re Suppres si on Water System . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 YA"!'.EE-ROWE I

- ~- - _ , - . _ , - . , , - - , , . . ..... ,____ _.,,_ ,,.__ , _ , . . _ . , _ , _ , _ l

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, i I OEX LIMITIllG CONDITIONS FOR ODEO. TION AND . SURVEILLANCE EEUI?E*'EN,TS i <

i .S__ECTI ON PAGE I t

. t l3/4.2.1 PEAK LINER HEAT GEt!ERATION RATE ................... 3/4 2-1 13 /4.2.2 NUCLEAR HEAT FLUX HOT CHANNEL FACTOR .............. 3/4 2-7 j3/4.2.3 t:UCLEAR EliTHALPY RISE HOT CHAtiNEL FACTOR .......... 3/4 2-9

!3/4.2.4 CNB PARA liETERS .................................... 3/4 2-11 l l

3/4.3 I f!S TRU.ENTATIC" REACTOR PROTECTIVE SYSTEM INSTRU"ENTATION ......... 3/4 a-i [

l3/4.3.1 3/4.3.2 ENGINEERED SAFEGUARDS SYSTEM IfiSTRUMEllTATI0tt ...... 3/4 3-11 i i l3/4.3.3 MONITORIf4G IllSTRui1ENTATION i Radiation Monitoring Instrumentation . . . . . . , . . . . . . 3/4 3-17  :

l I Incore Detection System ........................... 3/4 3-23 t'eteorol ogi cal I ns trumen ta tion . . . . . . . . . . . . . . . . . . . 3/4 3-24

~

. Fire Protection ................................... 3/4 3-27

' 3/4.4 t'AI" C00LAf 7 SYSTE!1 {

l 3/4.4.1 MAIN COOLANT LOOPS i l

l l Normal Operation .................................. 3/4 4-1  :

i I s ol a t ed L oo p . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-3

• Isolated Loop Startup ............................. 3/4 4-4 '

i 3/4.4.2 SAFETY VALVES - SHUTDOWN .......................... 3/4 4-5 l l

l j3/4.4.3 SAFETY VALVES - OPERATitiG ......................... 3/4 4-6 l'

!'l 3/4.4. 4 PRESSURIZER ....................................... 3/4 4-7  !

!3/4.4.5 11AIN COOLANT SYSTEM LEAKAGE ,

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Leakace Cetection Systers ......................... 3/4 4-8  !

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Operational Leakage ............................... 3/4 4-10  ;

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li;DEX ,

l!LI!!ITI!:G Ctb:~:0"S F0P. OEWIC'1 At;D SURVEILLAt'CE RE0VIREMEtlTS i

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': c T "' PAGE  ;

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3/4.7.10 FIRE SL'? PRESS 10il 1.'a t e r E ;'s ; c a . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-31 l i

Spray end/or Sprinkler Systems ............... 3/4 7-33  ;

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CO System ...................................

2 3/4 7-34 ,

Fire Hose Stations .... ...................... 3/4 7-35  !

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3/4.7.11 FIRE BARRIER pef 1ETRATI0fi FIRE SEALS 3/4 7-36  ;

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. i I":EX t

l BASES .

SECTION PAGE n

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'3/4.6 CONTAII.:'Ei;T SYSTEMS

/4.c., 7 :. : : aY 2. m : . .. =T . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 e-,

3/4.6.E C0:;TA:.. .E:.7 ISCLATI0tl VALVES . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-3 3/4.6.3 C0:'.5USTIBLE GAS C0iTROL .......................... B 3/4 6-3 3/a.7 FLAMT SYSTE"S .

3/4.7.1 TURBII;E CYCLE ..................................... B 3/4 7-4 3/4.7.2 STEAM GEi1ERATOR PRESSURE / TEMPERATURE LIMITAIOl1 .... B 3/4 7-4 3/4.7.3 PRI!'.ARY PU:'.P SEAL WATER SYSTEM . . . . . . . . . . . . . . . . . . . . B 3/4 7-4 3/4.7.4 SERVICE WAiER SYSTEi1 .............................. B 3/4 7-4 3/4.7.5 CONTROL ROCM VENTILATION SYSTEM EMERGEf!CY SHUTD0'.:il. B 3/4 7-4 3/4.7.6 SEALED SOURCE C0tiTAMINATION ....................... B 3/4 7-4 3/4.7.7 WA S T E E F F L U E f !T S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-5 3/4.7.8 EfVIRONMElTAL MONITORING .......................... B 3/4 7-6 3/4.7.9 SHOCK SUFFRESSCAS (S:.UEEERS) ...................... B 3/4 7-6 3/ 4. 7 .10 F I R E S U P P RES S I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-8 3/4.7.11 FIRE BARRIER PEllETRATION FIRE SEALS ............... B 3/4 7-8 3/4.9 ELECTDICol D'">ER SYSTEMS 3/4.8.1 A.C. SOURCES ...................................... B 3/4 8-1 3/4.8.2 0;! SITE PO'.-lER DISTRIBUTIO:' SYSTEM 5 . . . . . . . . . . . . . . . . . B 3/4 S-1 3/4.9 REFUELIi:G OPERATIOils 3/4.9.1 REACTIVITY ........................................ B 3/4 9-1 l l

3/4.9.2 I li S T RU: '.E NTAT I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 I YAN KEE-RC'. E XI

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SECTIC:. PAGE

, Censultants ........................................... 6-10 L'ee*.ing crervercy ..................................... 6-10 ceorem ................................................ 6-10 .

Review ................................................ 6-11 Audi;2 ................................................ 6-11 A u t h o r i ty . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-i2 Records............................................... 6-12 6.5  :::' _E ICCUPENCE ACTION ...........................

6-12

'6.7 SAFETY LIMIT VIOLATION ................................ 6-13 6.8 PROCEDURES ............................................ 6-13 6.9 REPORTIRG REOUIREMENTS

6. 9.1, 6. 9. 2, 6. 9. 3 ROUTINE REPORTS ....................... 6-14 6.9.4 REPORTABLE OCCURRENCES .............................. 6-16 6.9.5 UMIQUE REPORTING RE(UIREMENTS . . . . . . . . . . . . . . . . . . . . . . . 6-19 6.9.6 SPiCIAL REPORTS ..................................... 6-22 6.10 RECORD RETENTION ..................................... 6-23 6.11 RA C I AT I ON P ROTECT I ON P ROGRAM . . . . . . . . . . . . . . . . . . . . . . . . . 6-24 6.12 P.ES?IRATO.Y FROTECTIC" FROGRAM l'

6.12.1 ALL0dnNCE ........................................... 6-24 6.12.2 PROTECTIO:. PROGRAM .................................. 6-25 6.12.3 RE"0 CATION ......................................,... 6-27 l 6.1. s7

. U. T O.

. - . U Df****T.ro gr;rI ..................................

- .. 6,27 6.14 FIEE !!'0IECTION IMSFECIIC. ........................... 6-31 YAN KE E- RC'.lE XV

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DEFIflIT107:S__

l!:ra si. of -: a a race tcta and carma energies per disintegration (in l MeV) for 1sotores: -- tha.n ioairies, witn nalf lives gre'ater than 30 l minutes, naking up at least 95% of the total non-iodir,0 activity in the l ; coo ic.n. ' ,

...~r , -- e,.. . - .

,g . - - e.--..

, --c..eg,_

n M of- aemn pump; and distribution piping with associated sectionalizing control or isolation valves.

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YAitKEE-P.0!!E l-5 l

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ll INa inv..:. 4.u !C:!

FIRE DETECT'.0..-- .

lI l'ITI: 2 CC::JITIC:: FCR C?ERATION

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-.3...- . 'i . ....a icr er:n fire detection zone shown in Tcble 3.3-5 sn211 be 0:-ERA 3LE.

, i APP !CA21 LIT! At all 21..e5 . .an equip . nt in that fire dataction zone is requir?d to be OPERABLE.

IACTIOl:

With the number of OPERABLE fire detection instruments less than reqJired by Tcale 3.3 6:

1. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, establish a fire watch patrol to inspect the zone with the inoperable instrument (s) at least '

once per hour, and

2. Restore the inoperable instrunent(s) to OPERABLE status within 14 days or prepare and subait a special report to the Comaission pursuant to Specification 6.9.6 within the next 10 days outlining the cause of the malfunction and tha plans for restoring the instr :..ent(s) to OPERABLE status.

3. The provisions of Specifications 3.0.3 and 3.0.4 are not appli.:able.

SURVEILLANCE REQUIREMENTS

4. 3. 3. 4.1 Each of the above fire detection instruments shall be demonstrated OPERABLE:

a. At least once per 6 months by a CH13:':EL FU :: TIC':AL TEST, and I

b. At ler:.t c : 3 per 12 nonths by perfontance of a Cncnnal Calibration. l I

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I il i llYA?sEE R0'iE . 3/4 3-27 l

TABLE 3.3-6 I! FIRE DETECTION INSTRUMENTS l' (;;0TIFIEP, SYSTEU.)

ll MI! 4Il'U!1 It'STRUf'.E?lTS l;:,;STT,U:'.2:!T LOCliT:C:! OPERACLE ,

l'l.

i Centrol Pee- 5 . ,

ij2. Cable Spreacing I Cable Trav House 2 l'

..e ,L. 2 -

3. Sveitchgear P.cc, 9  ;

A. Diesel Generators  !

I No. 1 1 l'o . 2 1 I

ib 3 1 l'

l  ;

i

5. Safety Injection Pumps & l'c. 3 Battery 2 ii I '1 l!

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li ll Y! :.i',E E- R0'.'E 3/4 3-25 ,

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l' PLANT SYSTEMS 11 FIRE SLli.iE5 SIC... .

utaER S .m. .

7. .

.3.7.10.1 T'" ? ?.E SU ?M E^ E I"" ',NTE'. Sv5Tr shd1 be OPERABLE with;

a. 2 high pressure pu:1ps each with a capacity of 1000 spm. with their discharge aligned to the fire suppression header.

b. i.utcmatic initiation logic for each fire pucip.

I..

APPLIC A3ILITY: At all times.

ACTION:

a. With less than the sove required equipment, restore the inoperable equip,ent to OPERABLE status within 7 days or prepare ana suomit a Special Report to the Co nission pursuant to Specification 5.9.6 within the next 10 days outl iair.g the pl cas an . , . c.c : .. :r to be used to provide for the loss of reUJndancy in this system.

b. With no FIRE SUPPRESSION WATER SYSTE:1 OPERABLE, within q 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:

1. Establish a backup FIRE SUPPRESSION WATER SYSTE'4.

2. Notify the Commission pursuant to Specification l 6.9.6 outlining the actions taken and the plans and schedule for restoring the system to OPERABLE s te.tu s .

! c. Restore the F:RE SUPP?,ESSION UATER SYSTEM to CPERABLE I status within 14 days or prepare and submit a Special l Report to the Cociolission pursuant ta 3::cification 6.9.6 within the next 10 days outlining the cause of the alalfuiction ',nd the plans for restoring the system to CPER/.3LE status.

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i AYA',',E E -R O. E 3/4 7-31

lPLAUTSYSTEMS FIRE SUPVdIESIC -

l'AiER SYSTEM l

l 55un,diLLw.Cd ndyvinuicid5 t von cinued) ll,~,37,) -

---e.----e.4

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...- , 3v777:. Shall be dcaonstrated OPERABLE:

a. A; least once per 7 days by verifying the water supply volume,

b. At least once per 31 days on a STAGGERED TEST BASIS Dy starting each puup.

c. At least once per 92 d ys by checking OPEN the principal h: _cr cr.: c; .;;: : a i s;i a . i ?n . . i /e s .

d. At least once per 18 months by perfonnance of a system fl ush.

e. At least once per 18 months:

1. By performing a system functional test which includes simulated automatic start of the pumps, and

2. By ve:ifying that each psm; deveicos at icast 1000 gpm at a system pressure of 125 psig.

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?,"".E E-R0 !E 3/4 7-32

, PL A..T C' ~:  ; -

SPPSY A*10/09 SPRIllKLER SYSTEMS LIMITIliGC0ilDIT:d:1FOROPERATION 113.7.10.2 The followinc s m .. . s;rinkler systems located in the

. i;i i . t,.- _ . . . . 2. . / i. :

a. CAL'LE TPAY PTSE StVY SYSTEM. ,

APPLICABILITY: At all tirn when ecuipment in the area is required to De OPE.%6LE.

ACTIOi4:

a. 'lith a sprey and/cr sprinklar systcr in:perable establish a roving fire patrol to check the affected area (s) at least once per hc'.'r . _ ..+.; backup fire suppression equipment to tua cr2:,5,.

b. Rastore the system to OPEPaBLE stst.;s . ithin 14 da:"3 cr prepare and submit a Special Report to the Comission pursuant to Specification 6.9.6 within the next 10 days outlining the cause of inoperability arid the plans for riscoring the system to OPERABLE status.

SURVEILLANCE REQUIRE"E"TS 4.7.10.2 The spr5y and/or sprinkler systems shall be demonstrated to be OPEPABLE:

a. At least once per 92 days by cycling each testable valve through one complete cycle.

b~ At least once per 18 months:

1. By inspection of spray headers to verify their integrity.

2. By inspection of each nozzle to verify no blockage.

.I c. At least or.ce .cr 3 years by perforr'r; an air flow test through each j spray / sprinkler headcr ar.d verifying each spray / sprinkler nozzle is unobstructed.

O Y AZE E- PE.'E 3/4 7-33

T'. ANT SYSTEMS CO

,2 SYSTEM

,? . .:i;W CC::DITIO ! FC2 CPERATIO!;

ll: . .. . ..-...-- ... .. .....-. .-

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2 . 7. l '. . .; 7. . ms .. .

, 3  ;;., ._ ,;).2 +3 thall be CGERABLE lwith a miniaum we;ight of 213.5 pounds in the 2main C0 cylinder and 194.5 en~!s in t% m'vilivv C0; q.1iner, ,

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! APPLICABILITY: At all times when the ecuipment in the area is required to be OPERABLE.

ACTION:

a. With th: CO2 systc.a incper ble estabi sh fire patrol to check the af fected areaf's) aatrovina least once per hour, and provide backup fire suppression equip:r,ent to the area ( s) .

b. Restore the Systen to OPERABLE status within 14 days or prepare and subnit a Special Report to the Commission pursuant to Specification 6.9.6 within the next 10 days outlining the cause of inoperability and the plans for restoring the system to OPERABLE status.

SURVEILLANCE REQUIRElENTS 4.7.10.3 The CO2 system shall be demonstrated OPERABLE:

a. At least once per 18 months by verifying the weight of each CO 2 cylinder.

b. At least once per 18 months by verifying the system valves actuate manually. A brief flow test shall be made to verify flow from each nozzie. ("Puf f Test") .

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i PLANT SYSTE;iS ,

FIRE HU5E STATI0a3 .

' L u ;IT :..'. C;.;;;T:..] 7;1 C. E.' '.T:C'!

P l l 3. 7.10. 4 The fo11cuir,; f, ; hose st:tions shall be OPERABLE:

1. Outside the northwest door of the control roc.n.

2. Outside the northeest door of the control room.

APPLIC ABILITY: At all times when the equipment in the area is requirec to be OPERABLE.

ACTION:

With a hose station inoperable, route an additional equivalent capacity hose to the unprotected area from an OPERABLE hose

' s tr ui :r, s ti : i n 1 E ' ~

i SURVEILLANCE REQUIRE"ENTS ,

t 4.7.10.4 Each fire hose station shall be verified OPERABLE:

a. At least once per 31 days by visual inspection of the station to assure all equipment is available and the pressure in the standpipe is within limits.

b. At least once per 18 months by re.aoving the hose for inspection and re-racking.

c. At least once per 3 years, partially open each hose station valve' to verify valve operability and no

, blo:hage.

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': YANKEE-ROWE 3/4 7-35

t jiPLANT SYSTEMS .

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l' 2 . ~ . ', '. .s.  ; ._.. ;n ;n "ir; sarricrs ; rote:tir.g safety related l areas shall be functional.

A ~ ICAs!L:~;: n: al l ti.T.e s.

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t j a. With a penetration fire barrier non-functional, a roving fire patrol shall be established v:ithin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to check the affected are;(s) at least once per hour.

i b. The provisions of 3.0.3 and 3.0,4 are not applicable.

lS'X.'EILLANCE REQUIREMENTS l, - --

g --

h4.7.11.1 Penetration fire tarriers shall be verified to be

f. :;io.;ai by a vit..i in:pectien:

a. At least once ner 18 months, and

!! b. Prior to declaring a fire penetration seal functional following repairs or maintenance.

4.7.11.2 Penetration fire barriers that perform a pressure sealing function shall be verified to be functional by

perfor9ance of a local-leakage test prior to declaring a lipenetration fire barrier functional following repairs or

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..EE....,I 3/4 7-36

I lins,TRUMENTATION .

BASES .

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i T ' .- l .: .J.n .2 .. c e _c;i an sjs:sm ,ci th the specified minimum complement of equipment ensures that the

. : .r . - - . ;- s , ;, $ - - g f , - .

., e g u,i e es,7.q , 3;c. Fat?ly f represent the r:a:;;c ccra ,. .ar cistribution. Tae CPERASILITY of the neutron detectors is demonstrated prior to use by irradiatin; c;;h d:: ctor to be uscj and nor.r.alizing their outputs.

3_/4. 3. 3. 3 l'ETEOR0 LOGICAL INSTRUMENTATION 4

The OPERABILITY of the meteorological instrumentation ensures that suf ficient meteorological data is availab . fo r estimating potential radiation coses to the public as a result

. c:utine or accidental release of radioactive natorials to cha at'.;spiir: This capcbility is required to eva; sate the need for initiatir.g protective measure to protect the health '

and saf aty of the public (and is consistent with the j reco;amendations of Regulatory Guide 1.23, "0nsite l<.eteorological Prog rams" ) .

3/4.3.3.4 FIRE DETECTION INSTRUMENTATION CPE? N?'.L!TY of the fire 6:.?:tieq insta/~ tot 3t:09 e :ures that c equa:a 3rning capability is avcilaaie for tc.: poc c.a t detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire d2 tection instrumentation is inocerable, the establishment of frequent fire patrols in the af fected areas is required to provide da t ':!.i ?n c t,;; bili ty un til th2 i n :p:- ra'210 i n s t: rie n ta ti on i s returned to service. l 1 ,

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!jYA'. EE FC..E D 3/4 3-2

! PLANT SYSTEMS i

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CASES  ;

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,_.p. .e - ;-n sion sp tus ensures that adequate fire suppression capaoility is available to confine '

, 3 ,,. g _ _ , . . . n . . . .......:4- . . ,

--tir :f t's facility a

where saf ety rciat c:;;ipment is locaud. Tne fire suppression  ;

system consists of the rater system, spray and/or sprinklers, .

CO 2 , ano fire. nose stations. Tne collective capability of the  :

fire suppression syst:ns is adeq/cte to minimize potential daaage to safety related eoui,.nent ' .: is a major element in the  ;

i facility fire prmnion pr;;ra . ,

In the event that portions of the fire suppression systems ,

ere inoperable, alternate backup fire fighting equipment is )

required to be made available in the af fected areas until the i affa: xd c;,a;; e n cc.; be ec ::c 2: x scesica.  ;

In the event that the fire suppression water system becomes '

inoperable, immediate corrective reasures nust be taken since ,

'this system provides the major fire su,;pression capaoility of .

the plant. The requirement for a twenty-four hour report to  !

the Commission provides for prompt evaluation of the  !

tility of the corrective measures to provide adequate l tiri. suppression capability for the continued protection of the nuclear plant. i 3/4.7.11 FIRE BAPdlER PENETRATION SEALS i The functional integrity of the fire barrier penetration seals ensures that fires will be confined or adequately retarded j fror, spreading to adjacent portions of the facility. This design l feature minimizes the possibility of a single fire rapidly l l

involving several areas of the facility prior to detection and  !

I extinguish:ent. The fire barrier penetration seals are a passive llelement in the facility fire protection progra. and are subject l

to periodic ins .:tior.3.

During pari::s cf t1 ? Ten the n1s are not functional, j a fire patrol i3 r27 ;ir ' o . uimined until the af facted

• ll> seal is restored to functional status. +

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4jYANKEE-ROJE B 3/4 7-8 l

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I! 6.0 ADMINISTRATIVE C0'!TROI.S (C antin' ;d) l .

, c. Ali C'..~,C J.LTC ,l,T:,:.3 a .'Rr tha ini ti al f uel l oading

, shall be dirSctly superv'ised by either a licensed Senior N-. , .

_- ^ -

-' r 0, ;rct r Lini t:d 3,

. to Foal H1ndlina who has no other concurrent re s ,' - J uii ' . _ s .,  ; .ari.icn.

I

f. A 'i r' bef ': '

' 1---t C -- H -s sll be r: int 7ined c :i W at all tim.;s. This excludes 2 ccabers of the mini . , shif t crce nr:esn y for safe shutd:in of the plant and any personnel required for other essential functions during a fire emergency, l

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. . YAt:KE E-G.t E 6-2 .

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llADMINISTRATIVEC0tlTROLS

,,5.3 FACILITY SinFF W,.L:?;;/.7:43 i li -

' ' 5 . 2 . ',  :- .

r i .

• f 1i;te' 5 91 r -M11 Ilmaet or excao .. o . ,, v...iii,;s. ens s? '  : .12.1-1971 f: c; ; i uie ;:.i.ie m. .

I

3. Plcrt Su ?rint:# ' nt f b. Assistant Plant Superintendent 11

! c. Ch:mistry end Hacith Physics S.pervisor

d. Operations Supervisor

e. Reactor Engineer i

! f. Maintenance Supervisor

g. Instrument and Centrols Supervisors

h. Shift Supervisors

i. Plant Health Physicist 6.4 TRAltiltlG 6.4.1 A retraining and replacement training program for the Ifacility staff shall be maintained under the direction of the Training Coordinator and shall meet or exceed the requiraTients and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix " A" of 10 CFR Part 55.

6.4.2 A training program for the fire brigade shall be maintained under the direction of a member of the plant staff jappointed to perfor.a the duties of Fire Protection Coordinator en d shall n:et or ev.c nd t'a -- 'ec,ents of Section 27 of the

.lI;FFA Code - 1976.

6.5 REVIEW AND AUDIT l 6.5.1 PL A'!T OPE'J AT10'! R EVIE'A CC'"'.ITTEE ,

1 F' ::T !O': )

11 . )

i 6. 5.1.1 The Plant Operation Review Committee (PORC) shall 8 ' f unction to advis2 the Plant Superintendent on all natters g;related to nu-Icar saf etj.

C: : :Silla..

j ' 6. 5.1. 2 The Plant Operation Review Cemnittee shall be composed of the:

ri C' i :a n : Pl ant Sup 3ri.iiaaj.:n t 3; \;.. Ccair..an: Assist. int Plant E.;parintendent YA ..: : 9,0.iE 6-6

?

i i

i AC 0:ISTT.ATI'.'E CC: :LS I

• i b. Ths p.; cia.cc.cacc, L'cining cnd q.:lli ficaticn cf those -

j m:maers of In3 fa:ili ty stc f f .tho hava a direct

'-.: :::nticn, 93intenance or tec5'nic 21

!! aso? cts of th: :lc.nt, a t 1::n en:: pr 12 months, 3 'id :.

I

c. We r?rn ts Of actims t+en to correct deficiencies i occurring in facility equipacnt, struccures, syste.ns or method of operation that af fect nuclear safety at least once per 6 months,125%.

d. The perfont.ance of activities required by the Operational Quality Assurance Program to meet the criteria of A;;cndix "B",10 CFR 50, at least once per 24 months,125%.

, e. The Facility Emercency Plan and inplementing procedures at least once per 24 months,125%.

f. The Facility Inurity Plan and inplementing procedures I at least once per 24 nonths, i 25%.

g. The Facility Fire Protection Program and implementing procedures at least once per 24 months,1 25%.

h. Any other area of facility operation c nsidered i appropriate Dj the NSAR Committee or the Vice President.

i AUTHCRITY l 6. 5. 2.10 The NSAR Committee shall report to and advise the Vice President on those areas of responsibility specified in ll Sectiens 6.5.2.8 and 5. 5.2.9.

l REC: S

, j 6. 5. 2.11 Minutes of each NSAR Committee meeting shall be pre;2 red 37: f ar. :.-d:-d ca tha Vic 3 P. esier,t 2n j each ar._er i of the Committee for review within 20 working days following l'eachTesting. The reating minutes shall include, where

' ap;1icela, reports cf rctions enecm?3ssed by Section 6.5.2.8; lland reports of audits encompassed by Section 6.5.2.9. The review of t': H utas shall 5? co'ple%i .ti thin 60 days of the da t? i

of tPeir distributio . l l

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' ! 6. 6 RE;29 TABLE CCC m ET E ACTION

!!.6.1 6 Tne folic !in; actions shall be taken for REPORTA0LE CCCURENCES:

e. The Cc .ission shall be notified and/or a report submitted i pursuent to the requiremants of Specification 6.9.

.I i Y!,'P E E ? lE 6-12

/.D:'.: .',:: T - " :'.'I C ""* *_ : _ , _

l (d) Total dissolved gas radioactivity (in curies) and j average concentration released to the unrestricted j aped. l

(;-) T:nl /:h c (in litsr:) cf liquid .asta releasd.

h,l i

(f) Tctil vc (in lite s) of cilution water used prior to release from the restricted area.

1 (g) Total gross radioactivity (in curies) by nuclide released based on representative isotopic analyses performed.

(h) Farcent of Technical Specification limit for total radioactivity.

(d) Solid Wastes (a) The total amount of solid waste shipped (in cubic feet).

(b) The total estimated radioactivity (in caries) involved.

(c) Disposition including date and destination.

6.9.6 Special reports shall be submitted to the Director of the Office of Inspection anc Enforcement Regional Cffice within the time period specified for each report. These reports shall be submitted covering' the activities identified below pursuant to the requiretrents of the applicable eference specification:

a. Inservice Inspection Program Reviews, Specification 4.4.9.1.

b. ECCS Actuation, Specifications 3.5.2 and 3.5.3.

c. Inoperable ::eteorological : cr Merir; Instrumentation, Specifi-cation 3.3.3.3.

t

d. Scaled Scurce leaka;e in excess of limits, Specification 4.7.6.3.

e. Radioactive Solid Uaste Disposal, Specification 3.7.7.1.

f. Steam Generator ISI Results, Specification 4.4.10.6.

g. Environmental Prograr. Violation, Specification 3.7.8.

h. Fire Protec; ion and Suppression System f'alfunction, Specificati:rs 3.3.3.4, 3.7.10.7, 3.7.10.2, 3.7.10.3.

l YA::K?E-P" E 6-22

4 6.14 FIRE PROTECTIO.1 TNSPECTIO"

c. An indt:t-dent fire protection and loss prevention inspection and audit !!all be perfcrmea annually utilizing either qualified off-site licensee personnel or an outside fire protection firm,

b. An inspection and audit by an outside qualified fire consultant shall te perfon.ea at intervais no greater than 3 years.

4 M

YANKEE-R0'lE 6-31 l

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' U.S. NUCLEAQ REGULATORY Comi.;tS$10N DOCK UM R NRCFoRM 195 '

• G.76) {

NRC DISTRIBUTION roR PART 50 DOCKET MATERI AL TO: FROM: oATE OF DOCUM.:NT NRC Yankee Atomic Electric Co. 7/18/77 l Westborough, Mass DATE RECEIVED W. P. Johnson 7/21/77 -

R O RIZ E D P R OP INPUT FoHM NUMBER OF COPIES RECEIVED C5cc y 3 $[bMd l DESCRIPTION ENCLOSURE g gd Q//. #/

1 Enclosed propsed changeAto the Tech I Specs for fire protection to be consis-

}3,\\ g4' tant with the revised model Stahdard s Technical Specifications.

2p+23p rACKNOWLEDGED

t PLANT NAME: Yankee Rowe Nuclear Power Plant RBT 7/21/77 h (]I SAFEW FOR ACTION /INFORMATION ENVIRBNMENTAL l ASSIGNED ADe _

h r N ASSIGNED AD: V. MOORE (LTR)

/ noANEM CHIEFr C; a. .. ._ l 9 ) BRANCH CHIEF:

PROJECT MANAGER: + ' ' W" \ '# PROJECT MANAGER:

LICE'1 SING ASSISTANT: LICENSING ASSISTANT:

I B. HARLESS

, [ 7 INTERNAL DISTRIBUTION

/I_ M. vT' F R j SYSTEMS SAFETY PLANT SYSTEMS SITE SAFEW &

IM C HEINE$AN TEDESCO ENVIRON ANALYSIS I/ T Ar f 7.} SCHROEDER BENAROYA DENTON & MULL?R IpernLCOSSICK & STAFF l ENGINEERING TAINAS IPPOLITO CRt'TCMFTETA

/sut.wittro KNTCMT F. ROSA ENVIRO TECH.

Ivtor BOSNAK ERNST c cas SIHWELL OPERATING REACTORS BALLARD unvn DAWLICKI . STELLO YOUNGBLOOD

/ EIRENMifT DD9TFrT MANAGEFFNT REACTOR SAFETY /[ SHA0 _ _ _ _ . , _ . .

cvovMnt T ROSS /J BAER i P. COLLINS NOVAK 4 BUTLER GAMMILL (2) um!STON ROSZTOCZY ./ GRIMES urLTZ / CHECK SITE ANALYSIS ur'TrvrS VOLLMER ev AT&I BUNCH .

, SALTZMAN / J. COLLINS i RUTBERG KREGER

_ , ,, _ EXTERNAL DISTRIBUTION COffrROL NUMBE R l fiL? Rs (g >9& A ld. AffL i If TTC fl NSIC

/

___.3Al 1 AB I 772020326 RES IV (J. HANCHETT)l /2

/l 16 CYS ACRS SENT CATEGORY f/

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'4 F C F C R M 190(2 76)

,