ML20148J151

From kanterella
Jump to navigation Jump to search
Amend 10 to License DPR-3,including Change 115 to Tech Specs Re Addition of Limiting Conditions for Operation & Surveillance Requirements for Diverse Emergency Core Coolant Injection Actuation Channels
ML20148J151
Person / Time
Site: Yankee Rowe
Issue date: 11/27/1974
From: Goller K
US ATOMIC ENERGY COMMISSION (AEC)
To:
Shared Package
ML20148J149 List:
References
NUDOCS 8011210214
Download: ML20148J151 (7)
v • d • e


Text

-- ---

('.

(

Q::F

s

==

YANKEE ATOKIC POWER COMPANY .

I DOCKET No. 50-29.

' ~

6 YANKEE-ROWE

. T!=i-AMENDMENT TO FACILITY OPERATING LICENSE -

~

Amendment No. 10' License No. DPR-3 .

1. The Atomic Enet.gy Cotanission (the Commission) has found that:

4

~

A. The application for amendment by Yankee Atomic Power Company :g;;.

(the licensee) dated May 13, 1974, and supplemented by letters M dated September 5,1974, and October 4,1974, complies with . . . . . . .

the standards and requirements of the Atomic Energy Act of "EE; 1954,' as amended, and the Comission's rules 'and regulations i set forth in 10 CFR Chapter I; .

B. The facility will operate in conformity with the application, c. .:.;, .

the provisions of the Act, and the rules and regulations of' -

the Commission; "=" ~

' ~

C. There is reasonable assurance (i) that the activities authorized -

by this amendment can be conducted without endangering the .

health nnd safety of the public, and (ii) that such activities ,...

will be conducted in compliance with the Comissions regulations; 6 -

t ..

D. The issuance of this amendment will not be inimical to the f.

comon defense and security or to the health and safety of j:"

the public; and -

l1 E. Prior public notice of this areendment is not required since the amendment does not involte a significant hazards consideration.

[ _

F .

F:.

2. Accordingly, the license is hereby amended as indicated below:

A. Change Paragraph 3.A.(2) to read as follows: g

"(2) Technical Specifications

.=

The Technical Specifications contained in Appendix A, b

as revised, are hereby incorporated in the license.

The licensee shall operate the facility in accord-ance with th e Technical SI ecifications, as revised j orrec s * ...by . le eued--ch mges- thereto through-Change -Nor-115r"- 1

,wnwa ws > _

j oats

  • Forca AEC 318 (Rev. 9 5)) AECM 0240 W u. e. eovs awu sNT Pnentina orrsc s t ava.st e.ies ,,

I'

,.. . . -  :  :. . = 4~ -

, l 1 -

('

liEii-2- ~"

i --

-~ 1 :a B. Delete Paragralh' 4 and renumber Paragraph 5.as Paragraph'4.; ).:.;

is l C. Remova reference to Appen'ix A listed under Attachments.

l .

3. This license amendment is effectik; as of the date of its issuance. _

A FOR TIIE ATOKIC ENERGY COMMISSION

()riginal Signed by Earl Gollet Karl R. Goller, Assistant Director .

for Operating Reactors El Directorate of I.icensing .

Attachment:

Change No. 115 to Technical - - , . ~':::::

Specifications Date of Issuance: NOV 2 71974 55 4

?ll$

R_

9' a.

V:

};

is D

t:

f- *

+

h fe F.

gyRn46es > i.,

pars h ',

Form Asc.31s ;Rev. 9 5)) AECM 0240 W u. s. novsRNMENT PRINhMO OF FIC EI 1974.s36. lee ..

l l ,

r

( .

(' ,

. s

==:.

Ei

.b ATTACRMENT W LICENSE AMENDMENT NO. 10 .j CHANGE No. 15 E THE TECHNICAL SPECIFICATIONS (k((

/ FACILITY OPERATING LICENSE NO. DPR-3 3. : 7 YiNKEE A M MIC ELECTRIC COMPANY c' YANKEE-ROWE ATOMIC POWER PLANT DOCKET NO. 50-29 :rg 55... 4

=-.

"5 Revise The Technical Specifications as follows:  ;...g

1. Replace page 7a in Appendix A with the attached page. . =
2. Replace Table 1, " Reactor Protection System Setpoints," with the attached Table 1. =+= .
3. Replace page 509-2 in the Hazards Summary Report with the attached page.

LE l

t . .-

1:

t :.

k.

[. . .

ll 7 .;.

[ ..

t:::

E9.2 ki.

...V:'. Y.E. 

                                                                                                           ?':: T:

orvice > sunNawa > DATE F Form AEC 318 (Rev. 9 53) AECM 0240 W u. s. oova RNME NT PRINTINo OFFIC 861874 828140 . . . . 

                                                                                                           \l:

s G

7 

                                                          -7a-    .

( 

                                                         .-                  e                                     . .;           ._..=_.
a. ,
                                                                                                                   .,                 =.y 8:
b. An unexplained increase of 45 cps in the air ,.

k particulate monitor reading shall require 

  /

bringing the plant to a hot standby condition [: i to permit primary system inspection. { 3 : If both methods for determining main coolant icakage S become inoperative and an hourly schedule of local [:.'. sampling of vapor container air cannot be maintained, h the plant will be brought to a hot standby condition. [5 g 

                                                                         -                                                  S
                                                                                                                            !=..
6. Ot,her Plant Protection (1) The reactor shall be scrarr.ed outomat.cally, above 15 Fe! ,

cicetric , ,: hen the turbine 2.s tr.p. rec for any renscr.. The f turbine shall be protected by all u nal prote:tive tr.ps p;. 

                     ' including hagh threst bear:ng temperature, lou ocar:.ng oil pressu.re, low ccndenser. vacuum aha overspecc.

(2) The reactor shall be scran:.ed au;o:,.a . .cally, above 15 P.1 cicctr .c unen the generatcr : s t r:ppea for s:y :cas,:,r. . The generator shall be protec tcc ey all un.al pr M :,1ve tr:.ps including overcurrent,, c ff e'rentis t ar.d loss of f;cic. 

              "(3) Automatic initiation of the safety injection system, pumps and valves,'shall be set to operate at a main coolant pressure not
  • less than 1700 psig or a containment pressure not greater than 5 psig.
                                                                                                          }g I
             "(4)          The minimum nitror,cn overpressure on the Low preseurc                                                      .

Safety lojection Accumulator shall bc 410 peig. ,; i- ,- 

             "(5) The SuCety injection System shall be maintained in readiness to inject borated water into the reactor at all times when the main coolant pressure is                                      ,

1000 psig or higher." - L The reactor shall be scrammed automatically, when the pcwcr c E 

               "((>)

level is above 15 MWe, by two or more low steam generator level signals." . NOV 2 71974 l i-l l .

a 3 l  ! l l i. ~ 

                                                                                       >                                 l              'NOV27 g,       -

TABLE 1 - REACTOR PROTECTION SETPOINTS NO. OF CH ANNELS ' SET POINT LIMITS REPAIRS ~ ' YUNCTION REQUIRED TO TRIP .aYPASSES 1 out of 2 Auto bypass 5.2 doc / min - max. Minimum restart instrumen-High Startup Rate - Reactor Scram Above 15 MWe tation. . 2 source range channels ' 2 intermediate range channel None Neutron flux corresponds to 108% Minimum of 4 pperable High Heutron 2 c.c of 5 or 6 channels required for rated power - max. ,. Flux Level - reactor operation Reactor Scram 1 of 4 (single) 1 out of 2 None 1800 psig - min. Low Main Coolant m 6 Pressurizer Pressure - Reactor Scrams 80% of normal main cooland flow Low Main Coolant Not more than 2 out of 4 Manual bypass Below 15 MWe in any loop ~ min. - l Flow - Reactor Scram 1 out of 3 1 out of 1 Manual 200 inches - max. In service before in - High Pressurizer critical Water Level - Reactor Scram 

                               ~Not applicable         None              Available any time Manual -                                                                                                                                                     .

Reactor Scram Turbine Trip - Not applicable Manual bypass Usual Turbind Trip se't points Turbine trip scrams reactor - Below 15 MWe and trips generator above 

  'Reaccor Scram                                                                                                     15 MWe Generator trip scrams                               i Not applicable        Manual bypass     Usual Generator Trip set points Generator Trip -

Below 15 MWe reactor and trips tur '._.I ' Reactor Scram bine above 15 MWe ,_, Steam Generator 2 out of 4 Manual bypasa Not lower than 15 inches below ' Low Water Level 2 out of 3 Below 15 MWe normal vator level Reactor Scram ' Manual Turbine Not applicable Manual bypass Available any time above 15 MWe 

                                                                                                                                                           *i Generator Trip -                                   Below 15 MWe                                                       .

Reactor Scram 1 out of 3 or 4 Manus 1 1700 psig on main coolant system, Safety injection may be i Safety Injection initiated manually at l min.; 5 psig vapor container Operation any time pressure, max. Pressurizer Not applicable None 2485 psig, No. 1 valve ' max. , 2560 psig No. 2 valve - max.. ,_ _ Safety Valve >O _ _ ___ _ L _ _ _ _ _

l l l $ TABLE 1 { cent) - - 

                                                                                                            -                                                                              I REACTOR PROTECTION SETPOINTS NO. OF CHANNELS                                                                                   REPAIRS BYPASSES               SET POINT LIMITS FUNCTION      REQUIRED TO TRIP 5 psig vapor container pressure -        Closes trip valves in out-1 out of 2         None Vapor Coutainer                                            max.                                       going lines in vapor Outgoing Line Trip -                                                                                  container Valve Operation None             30*F temperature    d 'ifferential -     Prevents any isolated loop Main Coolant Valve     Not applicable                                                                 from being placed into max.

Interlock operation if the loop . temperature is more than 30*F lower than highest cold leg temperature in m the remaining loops ' W 9 -, 

                                                                                    ,O                                                                 .

4 

                                                                                                 .                                          :.,      "3;j                             .
                                                                                                   'i
                                                                                                                     /:j:       . ,1f.l;                     . l -
  • t-

, .- i- , B , ' . .- . . s' , e I . t 9 m 4 9

  • 6 s_ ,
                                                                                                                                     .,'_ c7-My, ' , . - .%
.,_,.cm...a           m  .w w-

                                                                                                $09:2-

[ j . i. 

                      .Routino Mochanical Te'sts_                                                      .

Control Rod Scrd - Circuit Check - Daring plont operation it is not advisabic to make any tests in the scram circuitry.. All indications that - are availabic will be noted at least once por shift, and adjustncnts will be made only if necessary. At no tianc will the scran circuitry be disconnected during operation. All rod scram tests will be nado during scheduled reactor-shutdoun or during various emergency shutdowris. 

                       '     Safety In.ioction System - Weekly, during power oparation, all of                     ,

the pumps EvTivos of the safety injection system will be operated individ-nelly from the safety injection control panel in the centrol roon to determinc their serviceability and correct light position indication. The punps will bc l l op3 rated only en by-pass to the cafoty injection-shield ttnk cavity uator stor- ' l age tenk. Loop fill valvas will only be opened with the injection va]ve closed l ti ght. All locked-open and locked-closed valves outside the vapor container 

              .uill bc checked at the conclusion of the tests to verify their correct position.                    :
             .1Tnonover the ret.ctor plant is shutdown and deprosuurized, ht e entire system                     J l

operntion will be checked by manual cperation of the. safety injection control f sid.tch provided on the nucler.r section of the nain control board. Darveillanco ' of the Safety Injection Actuation Signal (SIAS) Initiaticn Channels vill includo:

1. a comparison of tho separate pressure indicttions by each shift; 2. a, achannel sys-calibration ench refueling by applying known pressures to ecch sensor; 3 ten functional test each refueling by applicatien of, test signals to cach chanwl j to verify system ecpability; h. a nonthly operational check of the tuo contain-'

' - mont air pressuro switches. Pressuriner Sperv Systm - In order te assure reliabic perfor; nance, the preocurizer curcc end circulation spray systems vill be tested periodically, preforably during the norm 1 stcrtup cperaticn. VThilo naiutaining normal oper-nting conditions in tha nnin coolant systen and the precouro' control and relief sysian, that is with surCc sprcy doonergized,. it is detcrnined that correct circulction sprny exists (band centrol valvo initia]1y positiened so cs to nain-tain pressurizar equilibriun ecuditions) by not5ng frequency of heator cycling while nainttdning pressuriner at nc=al values. Verifict ticn of surga spray op3 ration vill b3 acccmplished by obtaining maxist sprcy f1cu cnd cbserving the resultant pressuriner pressurs decrocsc, tonpartture increcse of unter , 

                . flowing thrcuch the sm cc line, and ch:nces in pressurizer heatcr cycling.

P2 ensurizer 23enoid Relief V91'.c - Th3 pressuricer solenoid relief valvo, which is provi(.cd to limit the duty of the pressurizer safety valves, will be tested after refueling or dter cenpletion of maintenance on this valve. The set pressure and the blowdown pressure shall be observed during the test operation and shall be compared with the design conditions. After the valv'a has discharged, note the downstrem pipe temperatures to assuro that the valve disc has preparly resented. The stcan pressure required to test the solenoid relief valvo is ob-tained by operation of the pressuricer heaterr. Scram Alrrms Chack Points and Instrumntation Calibrction Checks - 

                                                                                              ~

l In order to assaro safe operaticn of tne plant, cortain instruncntation cII3cks will be perfor:md periodically. Only thoso checks that can be made without d.isconnecting the serrm circuit during plant operation vill be parformed. No tests or chacks will be made on any equipnent if there is a possibility of initiating a' f nisc serm. All calibration vill be nada before starling or dur-int scheduled shutdoun pariods, except where calibraticn is required at a peuer Icycl. NOV 271974}}

Retrieved from "https://kanterella.com/w/index.php?title=ML20148J151&oldid=3361748"