ML093630451
| ML093630451 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/09/1975 |
| From: | William Cahill Consolidated Edison Co of New York |
| To: | Goller K Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML093630452 | List: |
| References | |
| NUDOCS 8111040618 | |
| Download: ML093630451 (3) | |
Text
Consolidated Edison Comoany of New York. Inc.
4 Irving Place. New Ycrk. N Y 100i03 Telephone (212) 460-3819 September 9, 1975 Re Indian Point Unit No. 2
'Docket No. 50-247 Mr. Karl R. Goller, Acting Director For Operating Reactors Division of Reactor.Licensing U.S.
Nuclear Regulatory Commission Washington,.D. C. 20555 Dear Mr. Goller In response to your letter of August 7, 1975, Con Edison has reviewed its program for testing containment leakage.
Based upon this review, no design modifications to the plant-are recuired to meet 10CF-R Part 50, A-Dpendix J requirements.
Because these regulatCions were published after Con.Edison's containmert leakage test program was developed, modifications to the Technical Specijfications are necessary, and are presently being7 drafted.
Completion of these modifications are expected by Niolember 14, 1975. At that time, the proposed changes to the Technical Specifications will be submitted to the Commission.
Con Edison is currently scheduled to meet with the Regulatory Staff this month to discuss a number of items of interpre tation for a similar program that has been develoDed for Indian Point Unit No. 3. If changes are required as a result of that meeting, Con Edison will implement them for the Indian Point Unit 114o.
2 containment leaklIage test program prior to performing the next integrated leak rate test.
Very truly yours C-4 znrb William J.
Cahill, Jr.
v~ce.Prasident 8111040618 750331 AOK05O000.I.
Vice Picsden, '
~ 3 i2N-5,AJE p
7 requirenso 3.3.B-1 within the time period specified, the reactor shall be placed in the hot shutdown con dition utilizing normal operating procedures. If the requireme nts of 3.3.B-1 are not satisfied within.an additional*48 hours, the reactor shall be placed in the cold shutdown condition utilizing normal operating procedures.
- a. Fan cooler unit 23, 24, or 25 or the flow path for fan cooler unit 23, 24, or 25 may be out of service during normal reactor operation for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, provided both containment spray pumps are demonstrated to be operable.
OR Fan cooler unit 21 or 22, or the flow path for fan cooler unit 21 or 22 may be out of service during normal reactor operation for a period not'to exceed 7 days provided both containment spray pumps are demonstrated daily to be operable.
- b. One Containment spray pump may be out of service during normal reactor operation, for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, provided the five fan cooler units are operable and the remaining containment spray pump is demonstrated to be operable.
C. Any valve required for the functioning of the system during and following accident condition may be inoperable provided it is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 'and ali valves in the system that provide the duplicate function are demonstrated to be operable.
C.,
Isolation Valve Seal Water System The isolation valve seal water system shall be operable when the reactor Is critical.
O Weld Channel and Penetration Pressurization System The weld channel and penetration pressurization system shall be operable when the reactor is critical.
I 1 2.A C
C 0
- b.
Ale reactor is subcritical'. theteactor coolant system
- temperature and press ure shall not be increased more than 250F and.100 psi, respectively, over existing values.
C.
In either case, 'if the IVSW System is not restored to an
- operable status within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be brought to the cold shutdown condition utilizing normal operating procedures. The shutdown shall start 'no later than, the end of of the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period.
- 1. The reactor shall not be brought above the cold shutdown unless the electrical and mechanical penetrations and liner weld channels are continuously-pressurized above 41 psig.
- 2.
The requirements of 3.3.D.1 may be modified to allow any one header of the nitrogen or air pressurization system to be inoperable for a pe riod not to exceed 4 consecutive days.
J
- 3.
If the WC & PP System is-not restored to an operable status
- within the time. period specified, then:
- a. If the reactor~ is critical, it shall be brought to the.
- hot shutdown-condition utilizing normal operating pro
- cedur s.' The shutdown'shall start no later than at
- the end of the speci1fied.'time period.
- b.
If "the reactor is-suibcritical, the reactor coolant system
- temperature and press§ure, shall not be increased more than
- 250Fand 100 psi,. ras~activaly, over existing va.lues.
C.
- In either cdise; if the Vr~ & PP System is not restored
- toan operable status within an adaitional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be brouglit tc t:!e cold shutdown condition AP utilizing normal oilerati,ig procedures.
The shutdoyni shall
- start no later than- -the en1 of the 48 hoiur p:eriad.;