ML18142A565: Difference between revisions

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{{#Wiki_filter:ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGE 1~------,;8;,;.;5.:r0~7c.;;;i,.9.;;;0=3=0=9:---B-5_0_7_-c-12~---
{{#Wiki_filter:ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGE 1~------,;8;,;.;5.:r0~7c.;;;i,.9.;;;0=3=0=9:---B-5_0_7_-c-12~---
PDR ADOCK 05000280 P :PDR TABLE 4.1-1 (Continued)
PDR ADOCK 05000280 P :PDR TABLE 4.1-1 (Continued)
Channel Description  
Channel Description
: 10. Rod Position Bank Counters 11. Steam Generator Level 12. Charging Flow Check S(l,2) s N.A 13. Residual Heat Removal Pump Flow N.A 14. Boric Acid Tank Level *D 15. Refueling Water Storage Tank Level S 16. (DELETED)  
: 10. Rod Position Bank Counters 11. Steam Generator Level 12. Charging Flow Check S(l,2) s N.A 13. Residual Heat Removal Pump Flow N.A 14. Boric Acid Tank Level *D 15. Refueling Water Storage Tank Level S 16. (DELETED)
: 17. Volume Control Tank Level 18. Reactor Containment Pressure-CLS  
: 17. Volume Control Tank Level 18. Reactor Containment Pressure-CLS
: 19. Boric Acid Control 20. Containment Sump Level 21. Accumulator Level and Pressure 22. Containment Pressure-Vacuum Pump System 23. Steam Line Pressure N.A. *D N.A. N.A. s s s Calibrate N.A. R R R R R R R R R R R R Test N.A. M N.A N.A N.A. M N.A. M(l) N.A. N.A. N.A. N.A. M Remarks 1) Each six inches of rod motion when data logger is out of service 2) With analog rod position 1) Isolation valve signal and spray signal. . I -e e e ATTACHMENT 2 DISCUSSION OF PROPOSED CHANGE 1-.. e DISCUSSION OF PROPOSED CHANGE Technical Specification Amendments Nos. 95 and 94 (dated February 24, 1984) to operating licenses DPR-32 and DPR-37 for the Surry Power Station, Units No. 1 and 2 respectively, removed the surveillance requirements on the boron injection tank level instruments in Table 4 .1. Due to an administrative error, surveillance requirements for the boron injection tank level instruments were inadvertantly included in Technical Specification Amendments Nos. 97 and 96 on Table 4.1-1 (dated June 19, 1984) for Surry Power Station, Units 1 and 2 respectively.
: 19. Boric Acid Control 20. Containment Sump Level 21. Accumulator Level and Pressure 22. Containment Pressure-Vacuum Pump System 23. Steam Line Pressure N.A. *D N.A. N.A. s s s Calibrate N.A. R R R R R R R R R R R R Test N.A. M N.A N.A N.A. M N.A. M(l) N.A. N.A. N.A. N.A. M Remarks 1) Each six inches of rod motion when data logger is out of service 2) With analog rod position 1) Isolation valve signal and spray signal. . I -e e e ATTACHMENT 2 DISCUSSION OF PROPOSED CHANGE 1-.. e DISCUSSION OF PROPOSED CHANGE Technical Specification Amendments Nos. 95 and 94 (dated February 24, 1984) to operating licenses DPR-32 and DPR-37 for the Surry Power Station, Units No. 1 and 2 respectively, removed the surveillance requirements on the boron injection tank level instruments in Table 4 .1. Due to an administrative error, surveillance requirements for the boron injection tank level instruments were inadvertantly included in Technical Specification Amendments Nos. 97 and 96 on Table 4.1-1 (dated June 19, 1984) for Surry Power Station, Units 1 and 2 respectively.
The proposed change simply deletes the surveillance requirements from the text previously deleted by Amendment Nos. 95/94. The Safety Evaluation, concluding that no unreviewed safety question (as defined in 10CFR50.59) exists, remains unchanged from that supporting Amendment Nos. 95/94. In a similar manner, no significant hazards consideration as defined in 10CFR50.92 exists because the proposed amendment is administrative in nature and is similar to Example (1) of the examples provided by the Connnission (48FR14870) that are considered not likely to involve significant hazards consideration*.}}
The proposed change simply deletes the surveillance requirements from the text previously deleted by Amendment Nos. 95/94. The Safety Evaluation, concluding that no unreviewed safety question (as defined in 10CFR50.59) exists, remains unchanged from that supporting Amendment Nos. 95/94. In a similar manner, no significant hazards consideration as defined in 10CFR50.92 exists because the proposed amendment is administrative in nature and is similar to Example (1) of the examples provided by the Connnission (48FR14870) that are considered not likely to involve significant hazards consideration*.}}

Revision as of 10:26, 25 April 2019

Proposed Tech Specs,Deleting Surveillance Requirements for Boron Injection Tank Level Instruments
ML18142A565
Person / Time
Site: Surry  Dominion icon.png
Issue date: 07/12/1985
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML17159A880 List:
References
NUDOCS 8507190309
Download: ML18142A565 (4)
v • d • e


Text

ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGE 1~------,;8;,;.;5.:r0~7c.;;;i,.9.;;;0=3=0=9:---B-5_0_7_-c-12~---

PDR ADOCK 05000280 P :PDR TABLE 4.1-1 (Continued)

Channel Description

10. Rod Position Bank Counters 11. Steam Generator Level 12. Charging Flow Check S(l,2) s N.A 13. Residual Heat Removal Pump Flow N.A 14. Boric Acid Tank Level *D 15. Refueling Water Storage Tank Level S 16. (DELETED)
17. Volume Control Tank Level 18. Reactor Containment Pressure-CLS
19. Boric Acid Control 20. Containment Sump Level 21. Accumulator Level and Pressure 22. Containment Pressure-Vacuum Pump System 23. Steam Line Pressure N.A. *D N.A. N.A. s s s Calibrate N.A. R R R R R R R R R R R R Test N.A. M N.A N.A N.A. M N.A. M(l) N.A. N.A. N.A. N.A. M Remarks 1) Each six inches of rod motion when data logger is out of service 2) With analog rod position 1) Isolation valve signal and spray signal. . I -e e e ATTACHMENT 2 DISCUSSION OF PROPOSED CHANGE 1-.. e DISCUSSION OF PROPOSED CHANGE Technical Specification Amendments Nos. 95 and 94 (dated February 24, 1984) to operating licenses DPR-32 and DPR-37 for the Surry Power Station, Units No. 1 and 2 respectively, removed the surveillance requirements on the boron injection tank level instruments in Table 4 .1. Due to an administrative error, surveillance requirements for the boron injection tank level instruments were inadvertantly included in Technical Specification Amendments Nos. 97 and 96 on Table 4.1-1 (dated June 19, 1984) for Surry Power Station, Units 1 and 2 respectively.

The proposed change simply deletes the surveillance requirements from the text previously deleted by Amendment Nos. 95/94. The Safety Evaluation, concluding that no unreviewed safety question (as defined in 10CFR50.59) exists, remains unchanged from that supporting Amendment Nos. 95/94. In a similar manner, no significant hazards consideration as defined in 10CFR50.92 exists because the proposed amendment is administrative in nature and is similar to Example (1) of the examples provided by the Connnission (48FR14870) that are considered not likely to involve significant hazards consideration*.

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