ML19339A909
| ML19339A909 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 07/16/1975 |
| From: | Purple R Office of Nuclear Reactor Regulation |
| To: | Andognini G YANKEE ATOMIC ELECTRIC CO. |
| Shared Package | |
| ML19339A910 | List: |
| References | |
| NUDOCS 8011050685 | |
| Download: ML19339A909 (6) | |
Text
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$.h DISTRIBUTION JUL 161975 NRC PDR SVarga C
Local PDR aCRS (14)
Docket Readin DEisenhut Docket No. 50-29 ORB Reading j
KRGoller Yankee Atomic Electric Company fM ATlH: Mr. G. Carl Andtgnini, Assistant OIGE (3)
'T to the Vice President RAP 0urple i
20 Turnpike Road ABurger I 'k Westboro, Massachusetts 01581 SMSheppard r.
JRBuchanan Gentlemen:
TBAbernathy
,M We The proposed new format Technical Specifications which you submitted on g,. ;.
E January 3, 1974, include several sections concerning limiting conditions for operation relating to the integrity of the Yankee-Rowe primary coolant system pressure boundary and necessary surveillance requirements for maintaining this integrity.
In reviewing Sections 16.4.4, 16.4.14, T;:
4 f and 16.4.18, we have concluded that additioaal information requested in the enclosures is needed to continue our review. With respect to Section p,i
- W 16.5.7, we have concluded that this inservice inspection program for N
Yankee-Rowe is acceptable as proposed. Since an inservice inspection program is not presently included in the existing Yankee-Rowe Technical
- c 1 Specifications, we intend to incorporate it shortly by amending your i k' License No. DPR-3.
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You should file your response to this request for additional information h.t; in the usual manner as an amendment to your application.
Picase contact fy{
us if you desire additional discussion or clarification of the material k
rec,uer,t ed.
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Sincerely,
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Origbl signed by:
Robert A. Purple Robert A. Purple, Chief
[ig Operating Reactors Dranch #1 g
Division of Recctor Licensing (Qk ff
Enclosures:
7 1.
Request for Additional Information mj 2.
Model Technical Specification cc w/ enclosures:
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See next page o
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ENCLOSURE I
$t REQUEST FOR ADDITIONAL INFOR.\\t\\ TION YANKEE NUCLEAR POWER STATION (YANKEE-RONE)
DOCKET NO. 50-29 TECHNICAL SPECIFICATIONS
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1.
Specification 16.4.4 relates to temperature and pressure conditions
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during heat-up and cooldown of the reactor.
The temperature-pressure r
operating limitations for Yankee-Rowe are based on NDT temperature H
r plus 60 F.
In order to allow us to determine if the procedure used
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by you is as conservative as the requirements in 10 CFR Part 50, 1
Appendix G, you should provide the following information:
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t, a.
The naterial basis, including initial RTNDT, copper content and estimated fluence for the limiting material used to calculate the pressure-temperature limit curves, I
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b.
Provide the data points used to obtain Figure 16.4.4-2.
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Provide the relationship between accumulated reactor output (MNtH) c.
and fluence. The fluence may be taken as the maximum value on the gy vessel wall at 1/4T thickness.
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Indicate the material basis for Figures 16.4.4-1 and 2 on these
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- figures, w
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2.
Specification 16.4.14 relates to limiting conditions for operation GC; (LCO) of the reactor under varying rates and conditions of primary y[
coolant Icakage.
Specification 16.4.14A as proposed requires that at Icast two independent reactor coolant Icakage detection systems shall be in operation when the reactor is at power.
It is our position that RL the leakage detection system also shall be operating when the reactor is critical and at 2 perccht power in order to acceptably define the N
operating power level.
Please revise this LCO accordingly.
Specification 16.4.14B specifies a 10 gpm limit on primary coolant leakage to un-kifi?
contained systems. The existing Technical Specifications (Section D.2.d.13)
Af limits this leakage to 6 gpm.
Provide an explicit justification for the Yg proposed increase of this leakage limit.
M 3.
Specification 16.4.18 relates to LCO's with respect to oxygen, chloride k
and fluoride concentration in the primary coolant system.
The associated 30 surveillance requirements ar: included in Table 16.S.2-1 (items Ic g
and If).
It is our position that these LCO's and surveillance af 5
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. saum.qum-sem os
.. sy mmeeme-.ef***..a "Two
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requirements as proposed do not provide low enough concentration limits for operation of the reactor in the steady state mode.
In addition, the sampling frequencies for chemical analysis and the
,c corrective actions as proposed are not acceptable.
We have developed a model Specificati,on 16.4.18 (see Enclosure II) that would be acceptable to us for Yankee-Rowe.
Either confirm that you will adopt this model specification or propose a revised Section 16.4.18 and J
associated surveillance requirements that include comparabic require-1
- L ments and provide your justification therefor.
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