ML20034B719
| ML20034B719 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/20/1990 |
| From: | Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20034B720 | List: |
| References | |
| GL-88-06, GL-88-6, NUDOCS 9004300246 | |
| Download: ML20034B719 (8) | |
Text
l 10 CFR 50.90 l
GL'88-06
}
PHILADELPHIA ELECTRIC COMPANY NUCLEAR GROUP HEADQUARTERS 955 65 CHESTERBROOK BLVD.
i WAYNE, PA 19087 5691 1
(sis) soo sooo 4
April 20, 1990 Docket Nos.
50-277 50-278 License Nos. DPR-44 DPR-56 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555
SUBJECT:
Peach Botton Atomic Power Station Units 2 and 3 l
Supplement to Technical Specifications Change Request l
REFERENCE:
Letter from G. A. Hunger, Jr. (PECo) to USNRC dated July 11, 1989
Dear Sir:
In the above referenced-letter, Philadelphia Electric Company submitted Technical Specification Change Request (TSCR) No. 88-06. This TSCR consisted of two l
categories of Changes. The Category A changes involved removing the organization.
'j charts as recommended by Generic Letter 88-06, and the Category B changes were l
miscellaneous administrative changes. The purpose of'this letter is to amend the original TSCR. The attached revisions affect only the Category A changes, and' l
involve the following: 1) withdrawal of previously proposed Table of Contents pages vi and via, 2) revision of Safety Assessment for the shift crew composition and 3) addition of an asterisked note to proposed Table 6.2.1 " Shift Crew Composition -
Minimum Requirements" to ensure accurate interpretation of the. proposed Table.
L The following replacement pages for the original submittal referenced above are provided: pages 2, 6, 7, 9 and the List of Proposed' Changes for Attachment 1 I
the cover sheet for Attachment 2, proposed-Unit 2 Technical Specifications (TS) pages L
iva, vii and 245 and proposed Unit 3 TS pages iv, vii and 245. The vertical bars in the right hand margin of the pages in Attachment 1 and the cover sheet.to Attachment l-L 2 indicate changes from the original submittal. The vertical bars in the margins of the revised proposed TS pages refer to changes to the currently approved version of i
the TS.
I UVf 9004300246 900420 d)
PDR ADOCK 05000.277 P
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Document Control Desk April 20, 1990 TSCR 88-06 Page 2 The changes contained herein do not affect the Einding of No Significant Hazards Consideration, the Environmental lupact Assessment or the Conclusions previously submitted.
If you have any questions regarding this matter, please contact us.
Ver truly yours,
, b.
-2g% 1, G. A. Hunger, JF'.
Manager-Licensing Nuclear Engineering and Services Department
Enclosure:
Affidavit Attachments cc:
T. T. Martin, Administrator, Region I. USNRC J. J. Lyash, USNRC Senior Resident Inspector T. M. Gerusky, Director, PA Bureau of Radiological Protection i
I i
1 1
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- COMONWEALTH OF PENNSYLVANIA ss.
L CHESTER COUNTY D. R. Helwig, being first duly sworn, deposes and says:
l 1
l That he is Vice President of Philadelphia Electric Company, the Applicant.
herein; that he has read the attached supplement to request (No. 88-06) for changes to Peach Bottom Units 2-and 3 Facility Operating License Nos..DPR-44 and DPR-56, 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 and belief, i
j i
[
]
)%c Vice President i
Subscribed and sworn to 1
x before me thisJO day
$ N 6}1990.
of V
. [GYu' Anes)<f,j17,,
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Notary Public I
- l l
l NOTARIAL SEAL CATHERINE A. MENDE2. Notary Public L
Tredytfrin Two Chester County My Commissien Eytres Sect. A 1993
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l, DockGt No3.-50-277 i
50-278 i
1.
L License Nos. DPR-44 1
-DPR-56 1
1 Philadelphia Electric Company, Licensee under facility operating Licenses DPR-44 and DPR-56, for Peach Bottom Atomic Power-l Station Unit No. 2 and Unit No. 3, respectively, hereby requests that the Technical Specifications contained in Appendix A to the j
Operating Licenses be amended.
Proposed changes to the Technical Specifications are indicated by the vertical bars in the margins of the pages contained in Attachment 2 and listed here: IV (Unit 3
{
only), iva (Unit 2 only), vil, 243, 244, 245, 245a, 246, 252 and.
l i
l 252a.
L This application is submitted primarily as a result of Generic Letter 88-06 " Removal of Organization Charts from Technical Specification Administrative Control Requirements" which encourages licensees to propose changes to their Technical Specifications to remove organization charts from Technical. Specifications and replace them with descriptions of the organizational structure and characteristics which are important to safety.
The proposed changes concern the Administrative Controls in Section 6.0, and do not affect any Limiting Conditions for Operation or Surveillance Requirements.
The proposed changes in this Application are grouped into two categories.
Each category of changes includes a Description of Changes, a Safety Discussion and a Significant Hazards Consideration.
Category
'A' changes involve removing the onsite and offsite organization charts from Sections 6.2.1 and 6.2.2, respectively.
These changes are consistent with the guidance
.q.
Docket No3. S0-277 50-278-1 License Nos. DPR-44
)
DPR-56 replace it with "The facility organization shall be subject to the followings".
S.
Remove the onsite organization chart shown as Figure 6.2-2 (Sheets 1 and 2).
4 6.
Add Table 6.2.1 to show the' minimum shift crew composition.
This information was included in Figure _6.2-2 which is proposed-to be deleted.
7.
Delete the reference to Figure 6.2-2 in. paragraph 6.2.2.a and replace it with a reference to Table 6.2.1.
8.
Add paragraph 6.2.2.g which reads "In addition to the requirements of 6.2.2.a, the following shall hold a senior reactor operator license: 1) Plant' Manager or Superintendent-Operations, 2) Assistant Superintendent-Operations and 3)
Superintendent-Technical or Engineer-Systems."- This information I
was included in Figure 6.2-2 which is proposed to be deleted.
l 9.
Revise the Table of Contents pages iva and vil for Unit 2 and pages iv and vil for Unit 3 to reflect the deletion of Figures 6.2-1 and 6.2-2 and the addition of Table 6.2.1.._
e Docket Noo. 50-277
~
50-278
(
License Nos. DPR-44 DPR-56 Safety Discussion - Category
'A
I Deletion of the charts is accompanied by the addition of general ad;ninistrative control requirements which describe the l
l essential aspects of the organizational structure defined in the organization charts.
The additional administrative control descriptions are contained in the proposed paragraph 6.2.1.a through d.
They involve the designation of safety responsibilities and organizational freedom of the health physics, trainir.g and quality assurance groups.
The independence of the quality assurance group is further guaranteed by adherence to 10 CPR 50 Appendix B, t
Criterion I; l
t Removing the organization charts from the Technical Specifications will have a positive impac't on. safety by permitting a licensee to implement changes to its organizational structure without prior NRC approval provided that the change meets the general administrative controls and organizational objectives specified in proposed paragraph 6.2.1.
Consequently, enhancements to the organizational structure, as well as minor administrative changes such as position title revisions, can be implemented promptly upon identification of the need for the change.
Safety is 1.
.i
'l e
Docket Nos. 50-277 50-278 i
License Nos. DPR-44 DPR-56 10 CFR'50.34(b)(6) requires that the organizational structure, along with responsibilities and authorities,-be included in the Final Safety Analysis' Report.
Section 13 of the Peach Bottom Updated Final Safety Analysis Report (UFSAR)_contains the important organizational features currently depicted on Figures 642-1 and 6.2-2.
This information is required by 10 CFR 50.71(e) to be maintained and updated annually.
Thus, even in the absence of the organization.
charts from the Technical Specifications, there remains assurance that onsite and offsite organizations will be established and maintained to assure operation of the facility in a safe manner.
The proposed Category
'A' changes are considered to be j
administrative.
The management positions requiring an-NRC license do not change nor does the shift crew composition.
Further, the l
proposed Category
'A' changes do not increase or decrease the qualification, experience or training requirements of onsite or offsite nuclear personnel.
Significant Hazards Consideration - Category
'A' (1)
The proposed Category
'A' changes do not involve a significant increase in the probability or consequences of any. accident previously evaluated.
Lict of Propo3Md Chengna Section Affected Proposed Changes Page iv (Unit 3)
Designate Figures 6.2-1 and 6.2-2 as deleted.
Page iva (Unit 2) l-Page vli Add Table 6.2.1 to list.
Page 243 Paragraph-6.1.2 Add designation of Shift Supervisor as having control room command.
Paragraph 6.2.1 Change title "Offsite" to "Offsite and 0.1 site Organizations".
Delete existing paragraph 6.2.1 and add specifications 6.2.1.a through 6.2.1.d as recommended in GL 88-06.
Page 244 Delete Figure 6.2-1.
Paragraph 6.2.2 Replace "as shown on Figure 6.2-2 ands" with " subject to the following:".
Paragraph 6.2.2.a Replace reference to Figure 6.2 with a reference to Table 6.2.1.-
Paragraph 6.2.2 9 Add license requirements of station managers as required by GL 88-06.
Page 245 Delete Figure 6.2-2 Sheet 1-and add Table 6.2.1.
t Page 245a Delete Figure 6.2-2 Sheet 2-Page 246 Replace the Technical Engineer Paragraph 6.5.1.2 with the Engineer-Systems as a PORC member.
)
Page 2S2 Remove the " Office of the Chief j
Paragraph 6.5.2.9 Executive".
Page 252a Replace the " Executive Vice President-Paragraph 6.5.2.10.c Nuclear" with " Corporate Officer (s)".
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