ML20148F528

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Forwards Requests for Addl Info Re Proposed Tech Specs 16.2, 16.3 & 16.4.Proposed Tech Specs Should Be Updated to Reflect Changes Since 750104 & New or Modified Items in FSAR Should Be Identified.Requests Estimated Submittal Schedule
ML20148F528
Person / Time
Site: Yankee Rowe
Issue date: 05/20/1975
From: Purple R
Office of Nuclear Reactor Regulation
To: Andognini G
YANKEE ATOMIC ELECTRIC CO.
Shared Package
ML20148F531 List:
References
NUDOCS 8011050688
Download: ML20148F528 (5)
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Yankee Atomic Electric Company Mr. G. Carl Andognini, Assistant Q

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Westboro, Massachusetts 01S81

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Gentlemen:

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This is in reference to the proposed new format Technical Specifications &7 and the Final Hazards Summary Report (FHSR) rewritten in the Final Safety [,

Analysis Report (FSAR) for the Yankee Nuclear Power Station (Yankee-Rowe)  ;

which you submitted with your lotter dated January 4, 1974. ,i In the course of our ongoing review of your submittal, we have found W

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that we need additional information identified in the enclosures to this j.

1ctter. This initial request for additional information covers our <

review of your proposed Technical Specifications through Section 16.4.8. g We will send to you in the near future requests for other additional t s infomation including natters reisting to the remaining Sections in your \ f 4 proposed Teennical Specifications. r.

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In addition to the specific infomation identified in the enclosures, '

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we request that you update you proposed Technical Specification to reflect all changes to the existing Technical Specifications since January 4, 197S. ,' i$l{

$4 Your submittal of replacement pages would be acceptable for this purpose. 20k We also request that you list those requirements in the existing Technical Specifications t'aat you have either modified or omitted from your proposed b[,$

new format Technical Specifications and that you provide justification therefor. @%

JA. t With respect to the now FSAR we request that you identify all items of W safety significance that are new or modified compared to such items %g included in the FHSR.

'e l l Please provide us with an estimate of when you will submit the requested I .

infornation to us. Your estimate would aid us in planning our continuing b.:

review of your submittal.  % F vy,

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, .l 4 Yankee Atomic Electric Company. - 2^ .

' MAY 2 01975

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e in the, usual manner as an

.You'should file the additional.informat ion amendment to-your'. application. Please contact us if you desire additionil discussion or clarification of the material requested. f,5E Sincerely,  ;.;.

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Original signed by fi '

Ibobert A Purple . G, Robert A.' Purple, Chief Operating Reactors Branch #1 Division of Reactor Licensing p.

Enclosures:

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1. Request for Additional Information I',
2. Ph'R. Technical Specifications ~

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Mr; ' Donald G. Allen,-President [

Yankee Atomic Electric' Company 20 Turnpike Road

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Grconfield, Massachusetts 015S1 ,

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-ENCLOSURE I '. .

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  • REQUEST FOR ADDITIONAL INFOR'1\ TION

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YANKEE NUCLEAR POWER STATION (YANKEE-R0hE)- 'g DOCKET NO. 50-29 ,

TElfCNICAL SPECIFICATIONS ,

1. Specification 16.2.3.A-includes design features of the-reactor core ,

which are no longer applicabic. Revise this specification to reficct the design features of the operating reactor core that we have reviewed '

and approved. ,

2. Specificatka 16.2.3.B defines the design pressure and temperature of

Analysis Report the design pressure and temperature of piping and fitting.in the primary' coolant system are given as 2,285 psig and 5500F, respectively. Explain thi.s apparent discrepancy and revise this specification accordingly.

-3. Specification 16.2.4.C sets _ forth the design fcatt res of the containment purge system for venting the containment atmosphere following a LOCA.

This system includes an installed charcoal filter for which you have -

taken credit in the accident analysis. To ensure high confidence that this system will function reliably, when needed, at a degree of efficiency equal-to or better than that assumed in the accident analysis, you should propose Limiting Conditions for Operation and Surveillance Requirements for this system to be incorporated in the Technical Specifications. Enclosed for your guidance are model specifications (and bases) for the containment purge system (see Enclosure II) whi'ch meet current requirements. Since these were not prepared explicitly for Yankee-Rowe, some editing may be necessary to adapt them to the Yankcc-Rowe design and nomendature. ,

4. Specification 16.3.1 relating to limiting safety system settings for the Yankec-Rowe reactor protection system should define the setpoints for the

" Low Main Coolent Flow-Reactor Scram" in terms of parameters (current to the main coolant pumps) consistent wi,th the existing loss-of-flow instrumentation. The proposed setpoint. at 13 inches for the " Steam Generator Low h'ater Lcyc1" should be revised to 1S inches as given in-the existing Technical Specification'or you should justify this discrepancy. Present Technical Specifications include the setpoint  ;

(S.2 dec/minutc/ max) for the "lligh Startup Rate-Reactor Scram" which (

should also be inicuded in your proposed new format Technical Specifications. i Although you state in the basis that you have not taken credit for this l trip in the accident analysis, it is our position that its functional  ;

capability at the presently specified setting is required to enhance the .

overall reliability of the reactor protection system. Our position  !

would also apply to the nuclear overpower low setpoint and the turbine- i generator trip for which trip setpoints should be included in the Technical Specifications. ,

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. 4 S. The propose'dI ' Safety Limits-Reactor Core" in Specification 16.3.2 are  ;

no longer applicabic. Revise this specification and its associated basis to reficct the conditions analyzed by you and approved by us for .

.the operating Yankec-Rowc core. .

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V 6.- The proposed " Safety Limit-Reactor Coolant 16.3.3 is inconsistent with the concept of aSystem Pressure" safety limit in Specification b as defined in the regulations, since you did not allow a necessary margin between L the safety valve setting and the specified safety limit. Revise this '

specification, by either reducing the code safety valve settings to provide an acceptabic margin, or propose an appropriate higher value for

  • the safety limit, consistent with the provisions porritted by the .

applicabic codes for higher than the design pressures for the reactor .

coolant' system components (reactor vessel, piping, etc.). Revise the basis accordingly. l <

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7. h'ith respect to the incore instrumentation the existing Technical [

Specifications permit continued operation only with two .lcaking thimbles (incore detector pathways) isolated and out of service. All other incore instrumentation is required to be operable. The proposed LCO's in i Specification 16.4.1 " Core Instrumentation" would allow continued -

j operation with one moveable incore neutron detector operabic in one of [

the hottest instrumented fuel assemblics and with ten radial thermo-

. couple positions. Furthermore, continued operation would be allowed 2 definitely without the incore instrumentation operabic provided the '

pa nt load and the nuclear overpower trip setpoint are reduced by 10%.

To monitor power distribution and to verify that the total peaking factor (FQ ) remains below the specified limit the Yankee-Rowe incore instrumentation has.26 thercocouple positions and 22 incore pathways for the neutron i detectors. Please provide an evaluation that will show how you can accuratel determine with the proposed small number of operabic incore instrumen- ,

tation that Fq is below the allowable limit. You should also include information that will show that there will be assurance that the Fg will remain below the allowabic limit during operations not exceeding 900 ,

of full power to justify continued operation at that lower power level without Fq surveillance.

8. Specification 16.4.5 relating to LCO's for the " Chemical Shutdown and '

the Charging and the Volume Control System" requires operable components for baron injection to assure the capability for boron injection at a rato in excess of 132,000 ppm-gal / min. Provide an explicit basis for this specified minimum rate of boron injection into the reactor coolant.

The exception to the requirement to have two operable flow paths '

for boron injection when the reactor is critical, would permit operation with but one flow path when one reactor coolant loop is isolated.

Propose a time limit for this mode of operation consistent with the required use of the loop fill header and the charging pump, to reduce the time operation is allowed in this mode to a minimum. *

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9. Specification 16.4'.6 relating to LCO's for the " Emergency Corc! Cooling System";should be' revised to be more closely consistent with the .

(Maine-Yankee. Technical Specification 3.6 as applicabic to Yankcc-Rowe, Specifically, components in thclECCS required-for long-term reciircula-Ltion cooling'shall also be required.to_be operabic. -

10. lThe basis for Specification 16.4.7 '! Minimum Volume and Boron Concentration -

Safety Injection Tank" state that the analysis of. the loss-of-coolant incidents show that 77,000 gallons (to be transferred to the containment- ,

via core cooling before recirculatinn-is normally established).will be-

  • i sufficient to limit core temperatures and containment pressure for the *

. i s spectrum of breaks. Provide an explicit reference for this basis. . +

'11._ Specification 16.4.8 " Reactor Core Energy Removal" includes. requirements that the reactor shall not be at power unicss a minimum steam relieving capacity of 1,000,000 lbs/hr is availabic above 10% of full rated power

- and a minimum steam relieving capacity of 1,900,000 lbs/hr is availabic above 75% full rated power. The number of on-line safety valves.

providing these steam relieving capacitics should be specified. The l k

cxplicit basis to show that these relieving capacities arc. adequate to maintain the pressure in the turbino cycle components within allowabic limits of the ASME Code should be given.

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