ML19211D286

Application to Amend OL Re Tech Specs Relating to Core Monitoring,Core Flooding & Cooling Sys Operability Requirements for Assuring Safe Conduct of Refueling Operations.Certificate of Svc Encl

ML19211D286
Person / Time
Site:	Peach Bottom
Issue date:	01/14/1980
From:	Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML19211D285	List: ML19211D280 ML19211D286 ML19211D289
References
NUDOCS 8001170424
Download: ML19211D286 (8)

Text

- s BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of  :

Docket Nos. 50-277 PHILADELPHIA ELECTRIC COMPANY  : 50-278 APPLICATION FOR AMENDMENT OF FACILITY OPERATING LICENSES DPR-44 & DPR-56 Edward G. Bauer, Jr.

Eugene J. Bradley 2301 Market Street Philadelphia, Pennsylvania 19101 Attorneys for Philadelphia Electric Company 1762 277 so o t ivo+zt

BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of  :

Docket Nos. 50-277 PHILADELPHIA ELECTRIC COMPANY  : 50-278 APPLICATION FOR AMENDHENT OF FACILITY OPERATING LICENSES DPR-44 & DPR-56 1762 278 Philadelphia Electric Company, Licensee under Facility Operating Licenses DPR-44 and DPR-56 for Peach Bottom Atomic Power Station Unit Nos. 2 and 3 respectively, hereby requests that the Technical Specifications contained in Appendix A of the Operating Licenses be amended by revising certain sections as indicated by a vertical bar in the margin of attached pages 35, 47, 132, 139, 165, 227. 228, and 231; and by the addition of page 132a. Pages 228a, and 232 are included due to redistribution of material on the revised pages. A discussion of each of the requested changes is set forth below.

. .s CHANGE I It is anticipated that Peach Bottom Unit No. 2 and Unit No.

3 suppression chambers (torus) may need to be dewatered during future refueling outages to accommodate structural improvements and coating repairs to the torus. Such dewatering of the torus renders the LPCI and core spray systems inoperable as defined in sections 3.5.A.I.b and

, 3.5.A.3.b. Section 3 5.F.4 requires the operability of the LPCI and core spray systems during refueling operations; therefore, dewatering the torus would preclude concurrent refueling operations resulting in an extension of the plant outage. The p rop osed revision to section 3.5.F.4 adds an additional p rovision that would permit refueling operations and t orus dewatering to be perf ormed in parallel p rovided adequate core flooding inventory is available, and no operations are being perf ormed which have a potential for draining the reactor vessel.

The basis for this change is provided by the " Standard Technical Specifications for General Electric Boiling Water Reactors",

revision of April 1, 1978, section 3.5.4 page 5-8, which states that "the LPCS and LPCI systems and suppression chamber are not required to be operable p rovided that the reactor vessel head is removed and the cavity is flooded, the spent f uel p ool gates are removed, and the water level is maintained with the limits of specification 3.9.8 and 3.9 9. Specification 3.9.8 and 3.9.9 states that "At least (23) feet of water shall be maintained over the top of irradiated fuel assemblies seated within the react or p ressure vessel, and the spent fuel storage pool racks". The value of the parenthesized number may vary because of plant design, as stated in the Standard Technical 1762 279 Specifications. The Peach Bottom design provides for a minimum of 21 feet of water over the stored irradiated fue.? assemblies.

CHANGE II It is anticipated that the off loading of the entire reactor e

core p rior t o in vessel activities may be the most effective means of minimizing in-vessel work and personnel radiation exposure. The proposed changes to section 3.10.8 provide f or unloading and reloading the core under special conditions without having 3 counts per second (cps) on the s ou rce range monitors (SRM). The changes would enable the entire core to be unloaded and reloaded without the need for inserting portable " dunking chamber" monitors and a source, thus reducing the possibility of dropping items into the reactor. During unloading, the required shutdown margin will be assured by the fact that core reactivity is being reduced, and the control rods next to the fuel bearing region will be electrically disabled in the fully ins erted p osition. The changes would als o allow bundles to be reinserted to their p revious positions immediately adjacent to each s ou rce range monitor p rior to requiring 3 counts per second on the s ou rc e range monitors during reloading of the reactor. Operability of the s ou rce range monitors would be verified by a functional check prior to the beginning of fuel reloading.

A safety evaluation addressing the subject of the p rop os ed changes to Section 3.10.B is provided in the U.S. Nuclear Regulatory Commission's Safety Evaluation Reports supporting Amendment Nos. 33 and 30 to Facility License Nos. DPR-33 and DPR-52 for the Browns Ferry Nuclear Plant, Unit Nos. 'I and 2 respectively, dated September 13, 1762 280 1977; and supporting Amendment No. 66 to Facility License No. DPR-57 for the Hatch Nuclear Plant, Unit No. 1, dated June 12, 1979 As a consequence of this change, the Licensee p rop os es that the requirements of Table 3.1.1 regarding the react or p rotection system be waived when the reactor is completely defueled.

This application requests changes to the Peach Bottom Technical Specifiestions t o establish the core monitoring requirements, and the core flooding and cooling system operability requirements, for ensuring the safe conduct of refueling operations under various plant conditions. The prop osed amendment involves a sinFle safety issue having acceptability clearly identified by an NRC position and deemed not to involve a significant hazards consideration; therefore, pursuant to the requirements of 10 CFR 170.22, " Schedule of Fees for Facility License Amendment",

Philadelphia Electric Company proposes that this Application for Amendment be considered a Class III Amendment for Unit No. 2 and a Class I for Unit No. 3.

1762 281

___.__m m_._-m,... e, ---

The Plant Operation Review Committee and the Operation and Safety Review Committee have reviewed these changes t o the Technical Specifications and have concluded that they do not involve a significant hazard consideration, and will not endanger the health and safety of the public.

Respectfully submitted.

PHILADELPHIA ELECTRIC COMPANY -

/  !

By - - 's fih cT/ /

Vice PresidendI

~

l762 282

COMMONWEALTH OF PENNSYLVANIA  :

as.

COUNTY OF PHILADELPHIA  :

S. L. Daltroff, being first duly sworn, deposes and says:

That he is Vice President of Philadelphia Electric Company, the Applicant herein; that he has read the f oregoing Application for Amendment of Facility Operating Licenses and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information an: belief.

c

,p i

/'t /[ /~

/g Subscribed and sworn to SL before me this 10 day of * ^ ' * '

\Y l

~ 'bl0D o ry Pub l i

IDIAG P f

% co.

c-._,,** W3 J.a.m. 3q g gy 1762 283

CERTIFICATE OF SERVICE I cartify that service of the foregoing Application was made upon the Board of Supervisors, Peach Bottom Township, York County, Pennsylvania, by mailing a copy thereof, via first-class mail, to Albert R. Steele, Chairman of the Board of Supervisors, R. D. N o. 1, Delta, Pennsylvania 17314; upon the Board of Supervisors, Fulton Township, Lancaster County, Pennsylvania, by mailing a copy thereof, via f irs t-cla s s mail, to George K. Brinton, Chairman of the Board of Supervisors, Puach Bottom, Pennsylvania 17563; and upon the Board of Supervisors, Drumore T owns h ip , Lancaster County, Pennsylvania, by mailing a copy thereof, via first-class mail, to Wilmer P. Bolton, Chairman of the Board of Supervisors, R. D. N o. 1, Holtwood, Pennsylvania 17532; all this 14th day of January, 1980.

/ s i ,

v 4.'? _

_,( . #{ ,

hb' s Eugene J. Bradley Attorney for ,

Philadelphia Electric Company 1762 284