ML20214T607
| ML20214T607 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/01/1987 |
| From: | Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 161-00256-JGH-B, 161-256-JGH-B, NUDOCS 8706100343 | |
| Download: ML20214T607 (79) | |
Text
.
Arizona Nuclear Power Project P.O. box 52034
- PHOENIX, ARIZONA 85072-2034 June 1, 1987 161-00256-JGH/RJA U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C.
20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1 and 2 Docket Nos.: STN 50-528 (License No. NPF-41)
STN 50-529 (License No. NPF-51) 10CFR50.59 Annual Report for the 1986 Calendar Year File: 87-A-056-026; 87-032-404 1
Dear Sirs:
Attached please find a report of those changes at PVNGS Units 1 and 2 which were made pursuant to the requirements of 10CFR50.59 during the 1986 calendar year.
The attached report contains a brief description of such changes, tests, and experiments, including a summary of the safety evaluation of each change.
If you have any additional questions on this matter, please contact Mr. W. F. Quinn of my staff.
Very truly yours, 4
N J. G. Haynes Vice President Nuclear Production JGH/BJA/dlm Attachment cc:
- 0. M. De Michele (all w/a)
E. E. Van Br*st, Jr.
J. B. Martin R. P. Zimmerman i
G. W. Knighton l
E. A. Licitra A. C. Gehr (1
/
J. 4g 8706100343 870601 PDR ADOCK 05000529 g
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4
Attachment to 161-00256 This attachment contains a listing of the changes, tests, and experiments which were made pursuant to the requirements of 10CFR50.59 during the 1986 calendar year at Palo Verde Nuclear Generating Station (PVNGS) Units 1 and 2.
It should be noted that PVNGS Unit 3 was not licensed to operate during the 1986 calendar year, so no changes are reported for Unit 3.
A brief description of each change and a summary of the safety evaluation for each change is presented below. The listed changes did not:
(i) increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report; or (ii) create the possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report; or (iii) reduce the margin of safety as defined in the basis for any technical specification.
(1)
Description of Change Section 13.2.2.1 of the FSAR concerning the requalification of licensed personnel was revised to accurately reflect exanination and training.
The change reflects:
1) the requirement to conduct lectures for mitigating core damage on a biennial basis, 2) the addition of training for Station Blackout, and 3) the categories that are used for the annual written examination.
Other minor editorial changes were also incorporated.
This change was transmitted to the NRC in Amendment 15 to the FSAR.
Summary of Safety Evaluation The first change was made to document compliance with NUPEG-0737 and to provide consistency between the TMI Lessons Learned Implementation Report (LLIR) and the FSAR. The second change enhanced the program to address Station Blackout and the third change revised the categories to be in agreement with those used by the NRC and described in NUREG-1021.
These changes involved no unreviewed safety question since they are in compliance with NRC regulations and provide an enhanced description.
(2)
Description of Change Section 9B of the FSAR was revised to update the combustible loadings of several fire zones.
This change was transmitted to the NRC in Amendment 15 to the FSAR.
Summary of Safety Evaluation The combustible loadings of several zones were increased, however, protective measures such as suppression, detection systems and adequate fire barriers exist to nitigate the consequences of a fire.
The combustible loadings were required to be updated to reflect plant conditions to be in accordance with regulations. No unreviewed safety question was involved due to the reasons stated..
(3)
Description of Change Section 13.2.1.1.10 of the FSAR was changed to' delete the requirement for " classroom" review period and add the stipulation that during the review period there would be no other duties assigned.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation This change permitted more flexibility in allowing for appropriate training tailored to the needs of the individual.
This does not present an unreviewed safety question, since the candidates must still pass the examinations and the training is more suited to the individual needs.
(4)
Description of Change This change to the LLIR and Section 13A.26 of the FSAR incorporated item I.A.1.1 of the LLIR into a newly created Chapter 18 of the FSAR.
It updated the duties and reporting structure of the Shif t Technical Advisor (STA) _and consolidated the description into one location.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced.
The changes made were largely editorial and consistent with the NRC position as stated in NUREG-0737.
(5)
Description of Change The purpose of this change was to incorporate Section I.A.1.2 of the LLIR concerning Shift Supervisor administrative duties into a newly created Chapter 18 of the FSAR.
It was updated to make the Shift Supervisor position title consistent with Chapter 13 of the FSAR.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced.
This change was largely editorial in nature and consistent with the NRC position as stated in NUREG-0737.
(6)
Description of Change The purpose of this change was to update and incorporate Section I.A.1.3 of the LLIR concerning shift manning into a newly created Chapter 18 of the FSAR.
The section was updated to reflect title changes in the organization and include information discussed in the Technical Specifications.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced. This change was largely editorial in nature, presented previously reviewed material and was consistent with the NRC position as stated in NUREG-0737.
(7)
Description of Change The purpose of this change was to incorporate Section I.A.2.1 of the LLIR fato the newly created Chapter 18 of the FSAR.
This change concerns operator training and qualifications.
It was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced.
This change was largely editorial in nature and consistent with the NRC position as stated in NUREG-0737.
(8)
Description of Change The purpose of this change was to update and incorporate Section I.A.2.3 of the LLIR concerning training programs into the newly created Chapter 18 of the FSAR.
The section was updated to be consistent with Section 13.2.1 of the FSAR and Technical Specification 6.4.1.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced.
The change was largely editorial in nature, and was consistent with previously presented material and with the NRC position as stated in NUREG-0737.
(9)
Description of Change The purpose of this change was to incorporate Section I.A.3.1 of the LLIR into the newly created Chapter 18 of the FSAR dealing with the licensing examinations.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced.
This change was largely t itorial in nature, presented no new material and was consistent with the NRC position stated in NUREG-0737.
(10)
Description of Change The purpose of this change was to update and incorporate Section I.B.l.2 of the LLIR into the newly created Chapter 18 of the FSAR.
Sections 13.4.2.2, 13A.24, 13A.26 and 13A.27 which reference the Independent Safety Engineering Group (ISEG) at PVNGS were also a
updated.
The change reflects the reorganization of the Shift Technical Advisors and ISEG as described in a letter to the NRC dated July 2,1984 (ANPP-29874).
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The change described the function and purpose of the ISEG and was consistent with the NRC position as stated in NUREG-0737.
(11)
Description of Change This change incorporated Section I.C.1 of the LLIR into the newly created Chapter 18 of the FSAR.
It also updated the response to reflect history of the major effor:s done concerning the Emergency Operating Procedures (EOPs).
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The E0Ps were carefully generated in accordance with NUREG-0737 Supplement 1 guidance, Combustion Engineering Emergency Procedure Guidelines, and have been approved for implementation by the NRC staff.
This change merely documents that history and in no way alters the E0Ps.
(12)
Description of Change This change incorporated Section I.C.2 of the LLIR into the newly created Chapter 18 of the FSAR.
It updated the response to reflect commitments made to NRC resident inspectors concerning shift relief and turnover procedures.
This change was trcasmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The change was made in accordance with NRC guidance and documents our commitment to conscientious operating protocol.
(13)
Description of Change This change incorporated Section I.C.3 of the LLIR into the newly created Chapter 18 of the FSAR.
The change also updates the section to address concerns raised by resident NRC inspectors concerning Shift Supervisor responsibility.
It was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation This change presented no unreviewed safety question.
The change was made to be consistent with the NRC position stated in NUREG-0737.
The changes made added to the descriptions of the Unit Shift Supervisors duties to assure the safe operation of the plant.
(14)
Description of Change The purpose of this change was to incorporate Section I.C.4 of the LLIR into the newly created Chapter 18 of the FSAR.
This change concerning control room access was transmitted to the NRC in Amendment 16 to the FSAR.
Sumtary of Safety Evaluation No unreviewed safety question was introduced by this change.
The change was editorial in nature reflecting the fact that the commitments that were established in the LLIR are not satisfied.
The NRC staff had previously reviewed this material.
(15)
Description of Change The purpose of this change is to incorporate Section I.C.5 of the LLIR into the newly created Chapter 18 of the FSAR.
The response was revised to show that the ISEG has the overall responsibility for managing the operating experience review program at PVNGS.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The ISEG has the technical background necessary for implementing this program.
The change and the program were developed in accordance with the NRC position of NUREG-0737.
(16)
Description of Change This change incorporated Section I.C.6 of the LLIR concerning procedures for verifying correct performance of operating activities into the newly created Chapter 18 of the FSAR.
This change updates the response to reflect the fact that original commitments have been implemented. The change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
It was largely editorial in nature, updating responses to reflect that previously reviewed commitments were implemented.
(17)
Description of Change This change incorporated Section I.C.7 of the LLIR concerning NSSS vendor review of procedures into the newly created Chapter 18 of the FSAR. The changes made note that this requirement is satisfied by CE membership on TRRG and to note that ANPP has obtained CE review of the E0Ps.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation This change introduced no unreviewed safety question.
The change was made in accordance with the NRC position stated in NUREG-0737 and documents our commitment to regulatory guidance.
(18)
Description of Change This change incorporated Section I.C.8 of the LLIR concerning the pilot monitoring program into the newly created Chapter 18 of the FSAR.
The section was revised to reflect the fact that the requirement is no longer applicable to PVNGS Emergency Operating Procedures (EOPs).
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The change was made to reflect the NRC guidance of Supplement 1 to NUREG-0737. The NRC has conducted a review of the E0Ps in accordance with the reuqirements of item I.C.1 of Supplement 1 to NUREG-0737.
The change documented the fact that the pilot monitoring program was no longer required.
It has no impact on the safe operation of the plant or the implementation of the E0Ps.
(19)
Description of Change Section I.D.1 Of the LLIR concerning control room design reviews was updated and incorporated into the newly created Chapter 18 of the FSAR.
The section was updated to reflect activities that have taken place concerning this item for the past three years.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation This change did not introduce an unreviewed safety question.
It documented the activity in this area and revised the response to reflect the current status.
The activity has been done in order to meet the guidance presented in Supplement 1 to NUREG-0737. _._
(20)
Description of Change Section I.D.2 of the LLlR was incorporated into a newly created Chapter 18 of the FSAR.
This change updated information and history concerning the Safety Parameter Display System (SPDS) brought about by the new requirements of Supplement 1
to NUREG-0737 and correspondence.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation This change did not introduce an unreviewed safety question.
The information presented in this change was taken from submittals to the NRC staff dated February 27, 1985 (ANPP-32008) and August 19, 1985 (ANPP-33235).
The change was made to be in accordance with NRC guidance as stated in Supplement 1 to NUREG-0737.
(21)
Description of Change Section I.G.1 of the LLIR was updated and incorporated into a newly created Chapter 18 of the FSAR.
This section discussed training during low power testing.
The update to the response included the commiticents made by ANPP in a letter to the NRC dated November 10, 1982 (ANPP-22261).
The commitments were made to address NRC concerns. This change is included in Amendment 17 to the FSAR.
Summary of Safety Evaluation This change was made in accordance with the NRC position as stated in NUREG-0737.
No unreviewed safety question was involved.
The commitments made further enhance the training of operators and therefore, have no adverse effect on plant safety.
(22)
Description of Change Section II.B.1 of the LLIR was incorporated into the newly created Chapter 18 of the FSAR.
This change concerning the reactor coolant system gas vent system is editorial in nature and updated other FSAR sections to refer to the new chapter.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation This change does not introduce an unreviewed safety question.
It is editorial in nature, contains previously reviewed material and was intended to meet the NRC position of NUREG-0737.
(23)
Description of Change Section II.B.2 of the LLIR which addresses radiation levels and plant shielding was incorporated into
- a. newly created Chapter 18 of the FSAR.
Along with this change, the radiation zone maps in Chapter 12 of the FSAR were updated to reflect data collected from a survey of the plant. This change was incorporated into Amendment 17 to the FSAR. - -
Summary of Safety Evaluation This change was administrative in nature, and in accordance with the NRC position as stated in NUREG-0737.
The radiation zone maps were done in accordance with actual plant data and therefore, present a more accurate picture.
For these reasons, no unreviewed safety question was involved.
(24)
Description of Change Section II.B.4 of the LLIR was incorporated into a newly created Chapter 18 of the FSAR. A statement was added to reflect the training of radiation protection personnel.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation This change did not introduce an unreviewed safety question.
It was largely editorial in nature.
The change was made to document training for radiation protection personnel and to be consistent with the NRC position stated in NUREG-0737.
(25)
Description of Change This change updated the response to LLIR Section II.D.1 concerning performance testing of relief and safety valves and incorporated the section into a newly created Chapter 18 of the FSAR.
This change incorporates information gathered after the last LLIR update.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation The change did not introduce an unreviewed safety question.
The change documents our compliance with the NRC position as stated in NUREG-0737.
(26)
Description of Change Section II.D.3 of the LLIR which deals with the direct indication of relief and safety valve position was incorporated into the newly created Chapter 18 of the FSAR.
The section was also updated to reflect the fact that the commitments as previously stated have been satisfied for the units operating during 1986.
This change was incorporated into Amendment 17 to the FSAR.
Summary of Safety Evaluation This change was editorial in nature and reflected completion of previously reviewed commitments.
No new material was presented and the adherer.ce to the NRC position as stated in NUREG-0737 was maintained.
For these reasons, no unreviewed safety question was introduced.
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(27)
Description of Change Section II.E.1.1 of the LLIR was incorporated into a newly created Chapter 18 of the FSAR.
This change concerning the auxiliary feedwater system evaluation was editorial in nature and transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced.
This change incorporated previously submitted material in accordance with the NRC position as stated in NUREG-0737.
(28)
Description of Change Section II.E.1.2 of the LLIR concerning the auxiliary feedwater system was updated and incorporated into the newly created Chapter 18 of the FSAR.
The update only altered the wording so as to provide a more accurate description.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
It was largely editorial in nature and changed no operation or function of any equipment at the plant.
The change reflects compliance with the NRC position as stated in NUREG-0737.
(29)
Description of Change Section II.E.3.1 of the LLIR was incorporated into the newly created Chapter 18 of the FSAR. The section concerning emergency power supply for pressurizer heaters was updated to adddress each requirement stated in NUREG-0737.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The response was updated to address each NRC position as stated in NUREG-0737.
(30)
Description of Change Section II.E.4.1 of the LLIR concerning dc Mcated hydrogen penetrations was incorporated into the newly created tapter 18 of the FSAR. This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
No new material was presented.
The change was editorial in nature and consistent with the NRC position as stated in NUREG-0737..-
(31)
Description of Change Section II.E.4.2 of the LLIR concerning containment isolation dependability was updated and incorporated into the newly created Chapter 18 of the FSAR.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by the change.
The updated material reflects information to accurately describe the configuration and to make the section consistent with other FSAR sections.
This change is consistent with the NRC position as stated in NUREG-0737.
(32)
Description of Change Section II.F.1 of the LLIR which addresses accident monitoring instrumentation was updated and incorporated into the newly created Chapter 18 of the FSAR.
The updated information provided additional description and documented the completion of commitments previously made.
Minor editorial changes were made to other FSAR sections to appropriately reference the new section and provide consistency.
This change was incorporated into Amendment 17 of the FSAR.
Summary of Safety Evaluation This change was largely editorial and provided additional description to document ANPP compliance with the NRC position as stated in NUREG-0737.
Since the change was made in accordance with NRC requirements, the documentation of that fact does not constitute an unreviewed safety question.
(33)
Description of Change Section II.G.1 of the LLIR concerning emergency power for pressurizer equipment was incorporated into the newly created Chapter 18 of the FSAR.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The change presented no new material and was consistent with the NRC position as stated in NUREG-0737.
(34)
Description of Change Section II.K.l.10 of the LLIR concerning operability status was incorporated into the newly created Chapter 18 of the FSAR.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced.
No new material was presented in this change. It was found to be consistent with the NRC position as stated in NUREG-0737.
(35)
Description of Change Section II.K.2.13 of the LLIR concerning the thermal mechanical report was incorporated into the newly created Chapter 18 of the FSAR.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
No new material was presented.
The information is the same that was reviewed in the LLIR.
(36)
Description of Change Section II.K.2.17 of the LLIR concerning the potential for voiding in the reactor coolant system during transients was incorporated into the newly created Chapter 18 of the FSAR.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced.
This change was editorial in nature, presented no new material, and was consistent with the NRC position as stated in NUREG-0737.
( 37)
Description of Change Section II.K.3.2 of the LLIR concerning the safety effect of the power-operated relief valve isolation system was incorporated into the newly created Chapter 18 of the FSAR.
This change was transmitted to the NRC in Amendment 16 of the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced.
This change was editorial in nature and presented no new material.
(38)
Description of Change Section II.K.3.3 of the LLIR concerning reporting requirements related to safety valve failure and challenges to safety valves was incorporated into the newly created Chapter 18 of the FSAR.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The commitment was upgraded to report reactor coolant system safety valve challenges and failures in the monthly report as opposed to the yearly report. The decreased interval for reporting will not affect the safe operation of the plant.
(39)
Description of Change Section II.K.3.5 of the LLIR concerning the automatic trip of reactor coolant pumps during a loss-of-coolant accident was updated and incorporated into a newly created Chapter 18 of the FSAR.
The update to the section made reference to activity on the subject subsequent to the last amendment of the LLIR.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The change provides historical information.
No new naterial for review was presented and the change was largely for documentation purposes on the subject.
(40)
Description of Change Section II.K.3.17 of the LLIR concerning the report on outages of ECC system licensee report and proposed Technical Specification changes was updated and incorporated into the newly created Chapter 18 of the FSAR.
The update to the section reflected that previously made commitments were being implemented.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
Implementation of commitments concerning these reports has no affect on plant operation. The commitments were made consistent with the NRC position as stated in NUREG-0737.
(41)
Description of Change Section II.K.3.25 of the LLIR which addresses the effect of loss of alternating current power on pump seals was updated and incorporated into the newly created Chapter 18 of the FSAR.
The section was updated to make it consistent with Section 9.2.2 of the FSAR.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation This change introduced no unreviewed safety question. The change was largely editorial in nature and done to provide consistency with other material presented in the FSAR. __
(42)
Description of Chang Sections II.K.3.30 and II.K.3.31 of the LIIR were incorporated into a newly created Chapter 18 of the FSAR.
The sections were updated to document activity subsequent to previous amendments concerning these subjects.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The change was largely editorial in nature and updated the responses to reflect activity concerning these subjects. No material was presented in this change that has not been previously submitted. The change was made to document compliance with the NRC position as stated in NUREG-0737.
(43)
Description of Change Section III.A.1.1 of the LLIR which addresses the upgrade of emergency preparedness was updated and incorporated into a newly created Chapter 18 of the FSAR.
FSAR Section 2A.2 was also updated to reflect an i
accurate description of the meteorological system
.d make
.it consistent with the description provided in the emergency plan.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The description of the meteorological syscem was updated to reflect the present configuration.
The change was made consistent with the NRC position as stated in NUREG-0737.
(44)
Description of Change Section III.A.2 of the LLIR concerning long term emergency preparedness was incorporated into the newly created Chapter 18 of the FSAR.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
It was largely editorial in nature and censistent with the NRC position as stated in NUREG-0737.
(45)
Description of Change Section III.D.1.1 of the LLIR concerning the integrity of systems outside containment that may hold radioactive material was updated and incorporated into the newly created Chapter 18 of the FSAR.
The updated information provides consistency with other sections of the FSAR. This change has been transmitted to the NRC in Amendment 16 to the FSAR.
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4 Summary of Safety Evaluation No ' unreviewed safety question was ' introduced by this change.
The change was largely editorial and the updating reflected the completion-of previously made commitments.
Plant safety was not affected by providing consistency with other FSAR sections.
(46)
Description of Change
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<5 Section III.D.3.3 of the LLIR concerning iodine instrumentation.'was updated and incorporated into the newly created : Chapter 18 of ' the FSAR.
The updating reflected the _ implementation of previously-made commitments and clarification concerning the equipment.
s Summary of Safety Evaluation No.uoreviewed safety question was introduced by this change.. The change reflected appropriate clarification to accurately describe the equipment and operation of equipment.
The requirements of NUREG-0737 are still being met.
(47)
Description of Change p'G-1 Section III.D.3.4 of the LLIR which ~ ~ addresses control ' room habitability was updated and incorporated _ into the neuly. created Chapter 18 of the FSAR.
Other FSAR sections relating to; this subject (
were also updated.
The change was coordinated to reflect, actual as-built conditions and provide for consistency between sthet FSAR sections.
Detail was also added to provide ~ consistency with' the Emergency Plan. This change was incorporated into Amendment 17 to the s:
FSAR.
t Summary of Safety Evaluation
<g No new material was presented by_ this change.
It was largely J,
administrative to provide consistency and a
more, detailed i
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description.
The detailed description. adequately addresses ANPP N3y compliance with the NRC position as stated in NUREG-0737.
For these l ('y J reasons, no unreviewed safety question was involved.
i (48)
Description of Change This change ine'rporated the appendix to the LLIR into a newly creat$d, o
Chapter 18 of the FSAR.
The change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
his change was largely editorial in nature and made references to other sections of the FSAR.
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Description of Change Section 13.1.3.1. of ?.he FSAR was revised to reflect the addition of the position and associated qualification requirements for the supervisors in the Radwaste organization. This change was transmitted to the NRC in Amendment 16 to the FSAR.
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'SummaryofSafethEvaluation This revir,lon provided for a description of the radwaste organization to the same level of detail as other on-site groups.
The addition of i
the. radwaste. supervisor position does not introduce ar; unreviewed safety question.
The description was added so as to treat the organizations'in'a. consistent manner.
(50)
Description of Change
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2.5.4.10.1.2 wes The reference,for the effects of the\\ SSE in Section s
l See; ion 3.7;3.6.1.
Section 3.74326.1 was deleted previously,and i
certain,iaformation from this deleted section was' included. in Section 3.7.2.1.
This change will properly ' reference Section 3.7.2.1 'for ' ths effects of an SSE..The change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation
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The changp luas largely editorial.;, When Section 3.7.3.6.1 w( as n'eleted, t
the refe:ehce to that section'~ t was not properly updated; This clarification introduces no unreviewed safety question.
(51)
Descriptio of Change
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Section 11.3.1.1.6 of the FSAR was revised to reflect the fact that the flow controller for tiie gancous vaste system has a tolerance associated with it.
This change was transmitted to the NRC in Amendmend 16 to the FSAR.
2 Summary df' Safety Evaluation
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1 Waile the 'ilo.t - controller has an associated tolerance the release is minitored ' nd the limits are governed by the established criteria in a
10CFR20 and }10CFR50 Appendix 1I. i The, public health and safety will not be affected and'no unreviewed. safety question was introduced.
5 (52)
Description of Change I
1 Revise Table 6.2.6-3 conceining the containment isolation valve status durir.g Type A testing of containment ' penetrations numbers 25A and 25B from ' open to closed.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
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Summary of Safety Evaluation These valves close on a containment isolation actuation signal and the Type A test is to be in the containment isolation configuration.
This change does not affect the plant during operation, it only clarifies the configuration required for testing. No unreviewed safety question was introduced.
(53)
Description of Change Section 9.4.7.2 and Table 9.4-2 of the FSAR was revised to delete use of the atomizing water spray system during the testing of the diesel generators. This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation The atomizing water spray system is designed to maintain the temperature of the building below 120*F during diesel generator testing.
The change will not effect the operability of the diesel generators since tlay are designed to function in an environmental temperature of 140*F during essential operations.
No unreviewed safety question was introduced by this change since the function, i
purpose and operability of the diesel generators remain the same.
The atomizing water spray system is not credited in accident situations.
(54)
Description of Change Section 6.4.3.3 of the FSAR was inconsistent with Section 7.3.
Section 6.4.3.3 stated that CRVIAS was initiated automatically.
This was revised to accurately reflect plant design and provide consistency within the FSAR.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Saftey Evaluation No unreviewed safety question was introduced by this change.
The intent of the function of the equipment upon actuation remains the same. This section was inadvertently overlooked when Amendment 10 was issued.
This change also provides consistency with the Technical Specifications which do not acknowledge this signal as being automatic.
(55)
Description of Change Section 9B was revised to document an exception to Appendix R III.G in relation to the seismic gap area between the diesel generator building and the control building for the separation criteria. This change was transmitted to the NRC by letter dated November 21, 1986 (ANPP-39124) and included in Amendment 16 to the FSAR.
Summary of Safety Evaluation This change introduced no unreviewed safety question.
This determination was based on the fact that there are limited combustibles and no ignition sources and limited possibility of transient combustibles.
(56)
Description of Change Section 14B.41 and Table 9A-1 were revised to take exception to performing in-place leak testing on the containment normal clean-up HVAC system charcoal filters.
This change was transmitted by letter dated January 30, 1986 (ANPP-34868) and Amendment 16 to the FSAR.
Summary of Safety Evaluation The purpose of this system is to reduce the concentration of, airborne radioactivity in containment atmosphere prior to routine personnel access.
The criteria for personnel access is governed by remote radiation monitors.
No unreviewed safety question was introduced by this change since it does not affect the plant safety, personnel safety or the public health and safety.
(57)
Description of Change Section 14.2.5 was amended to clarify the review process of Phase I-IV test procedures.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change. The test procedures are still reviewed as required by the groups discussed in the section.
Test objectives, or acceptance criteria must be met and will be reviewed as described.
(58)
Description of Change In response to FSAR Questions 8A.15 and 14A.20, ANPP committed to:
" Measure the station distribution buses including Class lE buses unloaded and record voltages.
PVNGS will also measure and record the station distribution buses including Class lE bu.es upon loading the bus to at least 30%.
This will occur prior to initial full power reactor operation, consistent with Branch Technical Position PSB-1.**
The change made to PVNGS Unit 1 initial test program is to extend the completion date of measuring the station distribution bus voltages, loaded to at least 30%, from prior to initial full power operation until the completion of the PVNGS Unit 1 initial test program.
The measurement of the station distribution bus voltages in the unloaded condition has been completed.
This change was transmitted by letter dated January 8, 1986 (ANPP-34491) and Amendment 16 to the FSAR.
Summary of Safety Evaluation The transformer taps were set taking into account the expected offsite power source voltage variations and the maximum and minimum bus loading conditions as determined by the safety analysis.
Additionally, the time extension for completing this test does not change the safety analysis.
No unreviewed safety question was introduced based upon having the minimum specified independent and redundant A.C.
and D.C.
power sources and distribution systems as specified in General Design Criterion 17 of 10CFR50.
In addition to the above justification, actual experience and data obtained thus far through the Unit 1 Power Ascension Program validates the transformer tap settings for plant operation.
Plant equipment has satisfactorily operated both under steady state and transient conditions through a wide range of source voltages.
(59)
Description of Change FSAR Section 5A.20 was revised to address operator action outside the control room in achieving cold shutdown from the control room.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation The Appendix R Spurious Actuation Analysis determined that shutdown cooling isolation valves UV-653 and UV-654 needed to be de-energized during plant operation.
NRC Branch Technical Position RSB 5-1 allows for limited action outside the control room in achieving cold shutdown from the control room.
No unreviewed safety question was introduced by this change.
The operator action necessary is not critical to be performed in a short period of time.
(60)
Description of Change Sections 1.8 and 3.7.1.3, and Tables 3.9-5 and 3.9-6 were revised to incorporate the use of increased damping values in determining the acceptability of unrestrained piping uplif t at support locations and to reflect the modified support design loading combination equation.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation The use of increased damping values came as a v sult of the interim summary report by the Pressure Vessel Research Committee (PVRC).
The PVRC values were shown to be adequately conservative for use in this application.
The modified support load combination equations were based on either a linear elastic analysis or an elastic / plastic analysis.
The analysis was shown to have adequate conservatism.
NUREG-0484 also indicated the low possibilities of simultaneous occurrences of an SSE and a LOCA.
No unreviewed safety question was introduced since the piping was shown by acceptable analysis to be conservative.
This will not effect the safe shutdown or operation of the plant. -
(61)
Description of Change Section 5.4.10 and Figure 5.4-1 were revised and added, respectively, to incorporate the PVNGS specific pressure control program setpoints into the FSAR.
The pressure control program discussed in CESSAR does not accurately reflect the PVNGS program. This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The pressure control program given in Figure 5.4.10-5 of CESSAR is for a typical System 80 plant.
The PVNGS plant specific control points as given in Figure 5.4-1 of the FSAR reflect the actual plant operating conditions.
Setpoints specific to PVNGS have been previously submitted per CE Setpoint Document #N001-1.01-413.
Plant safety is not affected by the addition of plant specific information.
(62)
Description of Change Section 13.1.3.1 of the FSAR was changed to reflect the fact that the position of Operations Support Supervisor is a supervisor not requiring an NRC license.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation Since the Operations Support Supervisor does not directly affect the operation of the plant or the safe shutdown activities, an NRC Jicense is not required. No unreviewed safety question was introduced because the Operations Support Supervisor does not direct the licensed activities of licensed operators as defined by 10CFR55.4.
(63)
Description of Change Section 6.4.2.2.2.J of the FSAR was revised to increase the required closure times of the isolation dampers from 15 seconds to 35 seconds.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The requirud closure time as stated in the Technical Specifications is 180 seconds, which is well above thirty-five seconds.
Since, according to calculations, it would take the air 46 seconds to travel the ductwork to the control room after receiving the signal and the dampers take only 35 seconds to close, the operators would be in no risk to their health. --
(64)
Description of Change Section 11.2.2.4 of the FSAR was revised to accurately reflect the conditions ~ for taking the Liquid Radwaste System (LRS) demineralizer off-line and where the spent resin can be sent.
This change was transmitted'to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The primary purpose of this change was to clarify the bases for taking the LRS demineralizer off-line.
This allowed for judgement by a
supervisor, being able to react to conditions in a safe manner, being able to react to trends, not waiting for the system setpoints to be reached.
Since the system is not used for operation or safe-shutdown, this change is acceptable.
(65)
Description of Change Section 9B.2.15 of the FSAR was revised to allow for make-up water to the Essential Cooling Water, Essential Chilled Water and the Diesel Generator systems from the Fire Protection system should a fire damage both trains of circuitry.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
This change compensated for the risk of both trains being disabled by fire.
It increases the safety of the plant by providing compensatory measures in the event a fire should damage both trains of circuitry.
(66)
Description of Change Section 9.5.1.5.1, 13.2, and 13A were revised to reflect the current fire protection department changes to titles and responsibilities.
This change was transmitted to the NRC in Amendnent 16 to the FSAR.
Summary of Safety Evaluation The change introduced no unreviewed safety question.
The requirements for the fire protection department as stated in 10CFR50 Appendix R are still being met. The changes were largely administrative in nature.
(67)
Description of Change Section 9A.71 of the FSAR was revised to indicate that our secondary power supply for fire detection systems is designed in accordance with fire protection standards.
This change was transmitted to the NRC in Amendment 16 to the FSAR. - - - -
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
Previously, ANPP had selected one method suggested by the standard NFPA 72D for compliance.
The revision allows ANPP to comply by the use of either suggested method.
This change is in accordance with the fire protection standard.
(68)
Description of Change Section 1.9.2.4 of the FSAR was added to in order to note a deviation from Section 9.3.4.4 of CESSAR.
CESSAR states that all pumps of the Chemical and Volume Control Systems (CVCS) will be tested initially to demonstrate head and capacity.
PVNGS takes exception to that relative to the Boric Acid Concentrator (BAC) pumps.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation The BAC system is not a safety related system and is not required to mitigate the consequences of an accident or for safe shutdown of the plant.
No unreviewed safety question was introduced by this change.
The pumps were tested by the manufacturer and they were tested and qualified by C-E.
The pumps were also demonstrated operable during preoperational testing of the BAC.
(69)
Description of Change Section 13.2.1.5 of the FSAR was revised to clarify certain fire protection training requirements.
This change was transmitted to the NRC in Amendment 16 to the to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The section was revised so as to accurately state our compliance with the requirements of 10CFR50, Appendix R.
The change was administrative in nature. Plant safety or the operation of the plant was not affected, nor did it affect the effectiveness of the fire protection program.
(70)
Description of Change Section 9A.110 of the FSAR was revised to clarify our commitment concerning cable tray supports.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
Safe shutdown and safety related cable tray supports, as discussed in the response, are protected to ensure that fire will not affect the cables in the cable trays.
Safe operation will not be affected by this change. -
(71)
Description of Change Section 10.2.3.6.C was amended to reflect the change to the testing frequency of the turbine control valves from a weekly test to a monthly test. This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The vendor (General Electric) evaluated the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety and has found that there is only a negligible increase in the probability of a hypothetical missile with the decreasing of the testing frequency.
Furthermore, the architectural layout of Palo Verde makes turbine overspeed prevention an equipment protection function only and affects no safety related equipment.
(72)
Description of Change Sections 1.9.2.4, 9.4.4.2.2.11 and 14.2.12 of the FSAR were revised to reflect the fact that the dry sipping equipment is not currently being used at Palo Verde.
Therefore, the preoperational test will only be performed if the system is going to be used.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
Visual inspection of the fuel will be performed.
The dry sipping equipment was not used for the purposes of mitigating the consequences of an accident, but for detection purposes only.
(73)
Description of Change Section 14B was revised to delete the prerequisite stating that Phase I tests be completed.
Section 14B is describing Phase I tests.
It makes no sense to have a prerequisite the same as the test.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The revision was administrative in nature.
It had no affect on the testing progra.a or the operation of the plant.
(74)
Description of Change Sections 9B.2.11.9.5 and Table 9.5-1 of the FSAR were revised to note that the detectors may be photoelectric or ionization smoke detectors.
The change was made in two parts.
This change was transmitted to the NRC in Amendments 16 and 17 to the FSAR.
Summary of Safety Evaluation This change introduced no unreviewed safety question.
Some areas are not conducive to ionization type detectors and photoelectric detectors are required due to high velocity air paths.
In those areas, the photoelectric detectors more adequately perform their intended function of fire detection, and minimize the occurrence of false alarms.
(75)
Description of Change Section 1.8 of the FSAR was revised to document our compliance with Regulatory Guide 1.97, Revision 2.
Previously, the FSAR had not documented our position.
This change was transmitted to the NRC in Amendment lo to the FSAR.
Summary of Safety Evaluation The compliance to this regulatory guide is specifically stated for each variable.
The commitments are within the requirements of the regulatory guide, therefore, no unreviewed safety question was introduced.
(76)
Description of Change Section 1.8 and Table 5.2-3 of the FSAR were revised to incorporate the use of ASME code case N-71-12 to support the acceptability of material i che Unit 3 steam generator sliding base circular shims.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation The use of this code case was approved in Regulatory Guide 1.85 for the time period that the shims were installed.
No unreviewed safety question was introduced.
(77)
Description of Change Section 12.1.1.2 of the FSAR was revised to state position titles consistent with the titles used in other FSAR sections.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
This change was administrative only, to correct position titles and provide consistency within the FSAR.
(78)
Description of Change Section 14.2 of the FSAR was revised to reflect organizational changes and programmatic changes. The programmatic changes specifically state the use of administrative controls and procedures and allow for the transfer of systems to the Startup Department.
This change was transmitted to the NRC in Amendment 16 to the FSAR. - - -
Summary of Safety Evaluation The change is largely administrative.
All the responsibilities performed by the previous organization and program will be performed in accordance with this revision.
(79)
Description of Change Section 9.3.4 and Figure 9.3-13 of the FSAR were revised to add a dry reference leg for the Volume Control Tank (VCT) level transmitters and the automatic opening of CHE-HV-536 on low-low VCT level with the loss of power to CHN-UV-514.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation This change was a result of ANPP commitments.
(See SER Supplement 9).
The NRC has previously reviewed this material.
This was done as a safety enhancement.
Since it enhances the availability of the borated water suction source for the charging pumps, no unreviewed safety question was introduced by the change.
(80)
Description of Change Section 10.4.9.2.3 of the FSAR was revised to reflect the change of the auxiliary feedwater pump miniflow recirculation flow from 130 gpm to 300 gpm.
As a result, other system design data changed.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation The increase in the pump recirculation flow was done to reduce system noise and vibration.
No unreviewed safety question ' was introduced.
The function of the pump stayed the same.
It is within the system capability to handle the increased recirculation flow.
(81)
Description of Change Sections 1.8, 8.3 and 9.3 were revised to reflect the provision of Class IE power to valves CH-501 and CH-536.
The previous power supply to these valves was from a non-class 1E MCC that was shed from the Class 1E bus on SIAS.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety questions were introduced.
This change was made in order to provide further assurance that the charging pumps do not become gas bound on the VCT hydrogen cover gas following a loss of offsite power.
The change does not significantly reduce the amount of spare capacity of the diesel generators.
Thus, the emergency diesel generators are fully capable of performing their intended safety function.
(82)
Description of Change Section 9.5.1 of the FSAR was revised to more accurately describe ANPP post-operational testing of fire protection equipment.
The change also included a better description of the review process for making changes.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The change was administrative in nature and documented the fire protection program more accurately.
The program itself did not change, but the controls were better described.
(83)
Description of Change Section 8.3.1.4.1.lG of the FSAR was revised to include additional low energy circuits which have been evaluated to be low energy circuits that cannot cause the degradation of Class IE circuits in their vicinity.
The evaluation for the low energy circuits is included in Revision 1 of Bechtel Study 13-ES-600.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation This change introduced no unreviewed safety question.
It was performed in accordance with the requirements of Regulatory Guide 1.75.
The study discussed above shows that the additional circuits will not degrade Class IE circuits in their vicinity and therefore, will not affect the safe operation of the plant.
(84)
Description of Change Section 7.2.1 of the FSAR was changed to note that two of the preamplifiers for the excore neutron flux fission chambers are located outside of containment.
The CESSAR, which is referenced by the FSAR, incorrectly states that all preamplifiers are in containment.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation This change was made in accordance with Regulatory Guide 1.97.
The location of the preamplifiers is not a factor in the accident analysis. No unreviewed safety question was introduced.
The location of the preamplifiers does not affect the safe operation of the plant.
(85)
Description of Change Tables 6.2.4-1 and 6.2.6-3 and Figure 6.2.4-1 of the FSAR were revised to reflect the as-built condition of Penetration #7.
Penetration #7 is for a fire protection spray header. This change was transmitted to the NRC in Amendment 16 to the FSAR. - -.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
The change shows the correct piping configuration of a fire protection line that serves hose stations inside containment. The change has no affect on those systems used for safe shutdown of the plant nor does it affect compliance with any regulations.
(86)
Description of Change Section 1.8 of the FSAR was revised to take exception to Regulatory Guide 1.38, Revision 2 for the qualifications of QA/QC personnel who perform shipping damage inspections as described in Section 5.2.1 of ANSI N45.2.2-1972.
The exception exempts personnel from having to be qualified to perform a preliminary visual inspection prior to unloading to determine if any damage occurred during shipping.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation This change introduced no unreviewed safety question.
It involves the qualification of personnel performing preliminary visual inspections.
This will have no affect on the quality of equipment placed in the plant or on the safe operation of the plant.
Other inspections are performed prior to installation of equipment or components received.
(87)
Description of Change Figure 13.1-7 of the FSAR was revised to show that the number of security personnel is safeguards information instead of 105.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Fvaluation This change introduces no unreviewed safety question.
It is administrative in nature.
The change brings the FSAR into conformance with the requirements of 10CFR73.21(b)(xi) to protect information on "the size, armament and disposition of onsite reserve forces."
(88)
Description of Change Section 3.8.1.6.6.1.A.2.6 of the FSAR was revised to delete Table 3.8-3A and specific tolerance requirements for the oversize of fillet welds. This change was transmitted' to the NRC in Amendment 16 to the FSAR.
Summa y of Safety Evaluation No unreviewed safety question was introduced by this change.
The standards require the oversized fillet welds do not interfere with mating parts, but specific dimensions are not discussed.
ANPP still adheres to the standards.
Plant operation or safety related equipment are not adversely affected by this change since the welds will not affect any mating parts. -
(89)
Description of Change Section 11.2.2.4.1 of the FSAR was revised to indicate that flow from the low and high total dissolved solids holdup tanks is manually terminated upon a low level alarm as opposed to being automatically terminated as previously stated.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question is involved with this change. When the signal is received at 1000 gallons, the flow is manually terminated.
In the unlikely event that the operator fails to terminate the flow, at 500 gallons the flow is automatically terminated.
This change does not affect operation of the system, but provides a more accurate description.
(90)
Description of Change Section 12.5.2.2 1 of the FSAR was revised to show the change of equipment in the counting rooms.
The gas flow proportional counter was replaced by a scintillation type alpha counting system and the NaI detector was replaced with a
solid-state detector for the multi-channel analyzer.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation The change from the gas-flow proportional counting system to the scintillation counting system is based on the existence of a gas-flow proportional counting system in the chemistry laboratory counting room of each operational unit and duplication of this particular system is unnecessary.
The infrequent use of this type system by Radiation Protection is easily supported by the system in the chemistry counting room.
Replacement of the required NaI detector with the solid-state type detector will enhance the ability of the Radiation Protection Group to analyze and evaluate samples collected during the support of normal plant operations and samples required by PVNGS Technical Specifications.
Since these changes will either match or enhance previous capabilities, and they affect no safety related systems, no unreviewed safety question was involved.
(91)
Description of Change Section 13.2.2.1.2.B of the FSAR was revised to accurately describe the operator training program in view of the requiremants of ANS 3.1-1978.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation The ANPP training program for licensed operators is required per Technical Specification 6.4 to meet or exceed the requirements of ANS 3.1-1978.
The change to the description was to document full compliance.
Since this change provided for consistency between the Technical Specifications and the FSAR, and the standard was met, no unreviewed safety question was involved.
(92)
Description of Change Section 1.1.5 of the FSAR was changed to reflect the commercial operation date of the plant.
This change was transmitted to the NRC in Amendment 16 to the FSAR.
Summary of Safety Evaluation The date was changed to reflect the actual time commercial operation occurred.
This change was administrative in nature.
Since the required testing was completd at that time, no unreviewed safety question was involved.
(93)
Description of Change Section 11.5.2.1 and Figure 11.5-1 were revised to note the fact that the NSSS interface unit between the process radiation and gas stripper effluent monitors and the radiation monitoring system (RMS) mini computer. This change was incorporated in Amendment 17 to the FSAR.
Summary of Safety Evaluation By deleting the two monitors interface with the mini computer, the efficiency of the mini computer will be increased.
Both radiation monitors have alarms on the main control room annunciator panel, thus maintaining their function of warning the operator in case of increased radiation level.
For these reasons, no unreviewed safety question was involved.
(94)
Description of Change Section 9.5.1.2.2.H of the FSAR was revised to reflect an accurate description of the low pressure carbon dioxide system.
This change was incorporated into Amendment 17 of the FSAR.
Summary of Safety Evaluation This change was to clarify the description of the system operation.
The system still performs its intended function.
No commitments or level of fire protection have been reduced.
Therefore, no unreviewed safety question is involved..
(95)
Description of Change Sections 1.2, 8.1, 8.2 and 8B of the FSAR were revised to reflect changes that have been made to the PVNGS offsite transmission network.
The changes delete the Saguaro plant, add the North Gila substation, add the Westwing II line, and various other changes.
Additionally, new stability curves were given in Appendix 8B to reflect these changes to the grid system.
This change was incorporated into Amendment 17 of the FSAR.
Summary of Safety Evaluation These changes to the grid system have no effect on the ability of PVNGS to comply with the applicable regulatory requirements.
This change does not alter the availability of the two independent connections to.he grid which are required by various general design criteria (GDC).
Additionally, Branch Technical Position ICSB-ll requires licensees to do grid stability studies to demonstrate the stability of the grid following the loss of the largest single generating unit on the grid.
These studies have been performed with acceptable results.
The PVNGS transmission system meets the requirements of Technical Specification 3.8.1.1 concerning the availability of electrical power sources.
For these reasons, no unreviewed safety question was involved.
(96)
Description of Change Section 9.5.5.2.1.3 of the FSAR was revised to note the modification to the circuitry on the dier,el generator jacket water heater and circulating pump.
The modification ensures that the heater is off when the pump is not operating.
This change was incorporated into Amendment 17 of the FSAR.
Summary of Safety Evaluation The function and purpose of the system has not changed.
The modification was made for equipment protection.
The change prevents the jacket water heaters from burning up.
The change improves the reliability of the diesel generator system.
Therefore, no unreviewed safety question was introduced.
This change was discussed as number 201 in the report dated November 19, 1986 (ANPP-39097).
(97)
Description of Change Table 6.2.4-1 of the FSAR was revised to note the increase of the line size from one-half inch to one inch.
The line that was increased is the post accident sampling system (PASS) containment atmosphere return line to the containment. This change was incorporated in Amendment 17 to the FSAR. -
Summary of Safety Evaluation The increase la line size was made in order to ensure representative PASS samples.
The PASS samples are not used to prevent an accident nor to mitigate the consequences thereof. PASS is used for monitoring purposes.
Therefore, no unreviewed safety question was introduced by this system enhancement.
(98)
Descrip* ion of Change Table 11.4-3 of the FSAR was revised to acte the actual resin transfer dewatering pump capacity of 90 gpm as opposed to the previously stated, 75 gpm.
This change was incorporated into Amendment 17 of the FSAR.
Summary of Safety Evaluation The change was made to have the FSAR reflect the actual pump data.
This pump is not safety related and is not credited for accident mitigation. Therefore, no unreviewed safety question was involved.
(99)
Description of Change Figures 9.5-3 and 9.5-4 of the FSAR were revised tu show the anti-feedback delay unit and the blue strobe light on the evacuation system in high -. level noise areas.
This change was incorporated in Amendment 17 to the FSAR.
Summary of Safety Evaluation The changes were made as system enhancements. They were done in order to better provide for personnel safety in the unlikely case of an accident.
No equipment used for safe shutdown was affected.
Therefore, no unreviewed safety question was introduced.
This change was discussed as number 109 in the report dated November 19, 1986 (ANPP-39097).
(100)
Description of Change Section 9B of the rSAR was revised to incorporate changes to the emergency lighting system.
An extensive change to the emergency lis ting section was done in Amendment 16.
For personnel egress from a
areas not needed for operation of safe shutdown of equipment and those access and egress routes, 1-1/2 hour batteries are all that is required. These changes were incorporated into Amendment 17.
Summary of Safety Evaluation Emergency lighting with an eight hour capacity is installed in all areas of the plant required for safe shutdown.
Thus, the capability to bring the plant to a safe condition after an accident is ensured.
This change is in accordance with the applicable regulatory requirements and is not an unreviewed safety question. -
(101)
Description of Change Section 9.2.5.2 and Figure 9.2-2 were revised to show the correct projection of vertical concrete walls above the backfill and the correct water level for the spray pond.
These changes were incorporated into Amendment 17 of the FSAR.
Summary of Safety Evaluation This change was made to enhance the system.
The water level was increased so as to provide an extra margin of sufficient cooling for the safe shutdown and cooldown of the Unit.
The change does not affect the function and purpose of the plant.
It ensures that the essential spray pond water level has sufficient capacity to meet the requirements of Technical Specification Section 3.7.5.
Therefore, no unreviewed safety question was introduced.
(102)
Description of Change Table 6.2.4-2 of the FSAR was revised to increase the closure time for containment isolation valve CHB-HV-255 from 5 seconds to ten seconds.
This change arises from the fact that valve testing has shown the closure time to be greater than five seconds.
This change was incorporated into Amendment 17 of the FSAR.
Summary of Safety Evaluation CHB-HV-255 is the outside containment isolation valve for the seal injection line.
This valve does not close on a containment isolation actua;. ion signal and has no automatic functions.
Increasing the closure time for valve CHB-HV-255 has no effect on the safe operation of the plant and does not affect any of the previously evaluated accidents.
The subject valve is the outside containment isolation valve for the RCP seal injection line.
This valve is normally open and remains open following a CIAS.
The valve can be manually closed by the control room operator.
Isolation of this penetration is not needed and it is undesirable following an accident.
It is not desirable to lose seal injection flow during an accident due to the potential degradation of the seals from the relatively unclean RCS water flowing over the seals.
It is unnecessary to isolate this penetration since flow is into the containment, there are check valves inside containment to prevent backflow, and the operator has the capability to isolate the penetration if desired.
Therefore, no unreviewed safety question is involved.
(103)
Description of Change Table 9.5-1 and Sections 9B.2.12.4 and 9B.2.12.5 of the FSAR were revised to replace smoke detectors with heat detectors.
This change was incorporated into Amendment 17 of the FSAR. -.
Summary of Safety Evaluation Because of the steamy atmosphere in the main steam support structure, the smoke detectors gave false alarms.
The heat detectors were determined to be more accurate.
Both types of detectors provide the same function, therefore, no unreviewed safety question was involved.
(104)
Description of Change Section 9.1.4.2.2.17 of the FSAR was revised to indicate a bypass that is administratively controlled to the interlocks that prevent movement of the 10-ton fuel handling crane unless the hoist is at its upper limit. This change was incorporated into Amendment 17 of the FSAR.
Summary of Safety Evaluation This change does not affect the load bearing capabilities of the crane.
Damage to fuel assemblies are precluded by administrative 1y prohibiting the use of the bypass when a fuel assembly is not completely above the storage racks or New Fuel Elevator.
The bypass will allow for ease in alignment and other such activities.
For the above stated resaons, no unreviewed safety question was introduced.
(105)
Description of Change Section 9.5.5.2 of the FSAR was revised to note the modification of the cooling water supply and return lines to provide higher temperature cooling water from jacket cooling water in lieu of spray pond water to the diesel generator governor oil cooler.
This change was incorporated into Amendment 17 of the FSAR.
Summary of Safety Evaluation Vendor concurrence was received to make the change to use the higher temperature cooling water.
The change was made to improve the i
performance of the system.
The higher temperature water is more suitable for this system. This change was reviewed and documented by the NRC in a letter from Michael J. Davis (NRC) to Mr. E. E. Van Brunt (ANPP) dated March 16, 1986 [ sic, 1987].
This change does not involve an unreviewed safety question.
This change was also discussed as number 77 in the report dated November 19, 1986 (ANPP-39097).
(106)
Description of Change Figure 11.2-1 of the FSAR was revised to show that there is no line off the discharge header of the anti-foam pump to the Boric Acid Concentrator.
This change was incorporated into Amendment 17 of the 7SAR..
Summary of Safety Evaluation This line was never installed because an evaluation had determined that getting rid of the anti-foam agent in the reactor coolant system was not practical.
No safety function or plant performance parameter had been associated with that line.
Therefore, no unreviewed safety question exists.
(107)
Description of Change Sectfons 3.1.4, 3.6, 3.9 and 5.1 of the FSAR were revised to update the FSAR to reflect the final rule of the modification of General Design Criteria 4.
This change was incorporated into Amendment 17 of the FSAR.
Summary of Safety Evaluation Analyses were submitted on the CESSAR docket to support deleting the requirement for pipe whip restraints on the reactor coolant system piping.
These analyses support the fact that no unreviewed safety question was introduced.
(108)
Description of Change Table 9.2-8 and Section 9.3-4 of the FSAR were revised to correct cooling water requirements and change the operating pressure in the Reactor Drain Tank (RDT) to.5 psig.
For the gas stripper the cooling water requirement was changed from 700 gpm to 500 gpc and for the pressurizer surge line sample cooler, the cooling water requirement was changed from 26 gpm to 30 gpm.
These changes were incorperated into Amendment 17 to the FSAR.
Summary of Safety Evaluation No unreviewed safety question was introduced by this change.
By changing the RDT operating pressure, it eliminated unnecessary flow of nitrogen gas to the RDT. Regulations are still complied with and the change does not affect equipment used to mitigate the consequences of accidents.
The cooling water requirements, though different from CESSAR, were transmitted to PVNGS in another document to ensure good performance of equipment. These raquirements also, do not effect the safe shutdown of the plant or the mitigation of the consequences of an accident.
(109)
Description of Change Sections 6.2.4.3, 9.3.4.1 and 9.3.1.2.1 of the FSAR were revised to reflect that the reactor coolant pump sapport systems isolate on a CSAS as opposed to a CIAS.
This change was incorporated in Amendment 17 to the FSAR. -
Summary of Safety Evaluation With this change, the redundancy of isolation is maintained and continued RCP seal bleedoff operation serves to better maintain the integrity of the RCS pressure boundary.
The fail safe positions of all of the valves are maintained and no new leakage paths are created by this change.
For these reasons, no unreviewed safety question was introduced.
(110)
Description of Change Section 6.5.1.4.2 of the FSAR was revised to accurately list all the references to the Technical Specifications.
This change was incorporated in Amendment 17 to the FSAR.
Summary of Safety Evaluation This change was administrative in nature.
Listing appropriate references to the Technical Specifications has no effect on plant safety. Therefore, no unreviewed safety question was introduced.
(111)
Description of Change Figure 9B-38 was revised to reflect that there is no wheel type fire extinguisher located on Elevation 176' of the turbine building.
This change was incorporated in Amendment 17 to the FSAR.
Summary of Safety Evaluation No credit was given for a wheel type fire extinguisher on Elevation 176' of the turbine building in the Fire Hazards Analysis.
There are no regulatory requirements for having it there.
Therefore, no unreviewed safety question was involved because of this change.
(112)
Description of Change Section 1.9.2.4 of the FSAR was revised to reflect a change to the test method for the Unit Load Rejection Test for Units 2 and 3.
The method was changed so as not to obtain a turbine overspeed condition, but to be able to test the fast bus transfer feature.
This change was incorporated into Amendment 17 of the FSAR.
Summary of Safety Evaluation The circuitry for arresting an overspeed condition had been tested on Unit 1 and functionally tested for the other units.
The fast bus transfer was a critical item which required testing.
Since the test objectives and acceptance criteria remained the same, this change was acceptable. No unreviewed safety question was introduced. 1
(113)
Description of Change Section 14B.10 of the FSAR was revised to clarify the fact that each battery in the emergency lighting system would be tested to its required duration.
This clarification was provided at the request of the NRC.
The change was transmitted to the NRC in a ' letter dated December 19, 1986 (ANPP-39453).
Summary of Safety Evaluation This change vas initiatt.d to provide clarification to what was required and intended.
It is an administrative change. No unreviewed safety question was involved.
(114)
Description of Change FSAR Section 1.8 was revised to take exception to Regulatory Guide 1.108.
The exception introduces an alternative method to determine test frequency. This change was incorporated into Amendment 17 of the FSAR.
Summary of Safety Evaluation Generic Letter 84-15 endorses the alternative method to determine test frequency of the diesel generators.
By reducing the test frequency, it is expected that the reliability of the diesel generators will be improved.
For these reasons, no unreviewed safety question was introduced.
(115)
Description of Change Sections 6.4.2.2.2, 6.4.2.4, 6.4.4.3 and 6.4.6 of the FSAR were revised to delete the dencription of control room door alarms providing alarm indication that control room doors were open after actuation of essential ventilation. This change was incorporated into Amendment 17 to the FSAR.
Summary of Safety Evaluation Regulatory requirements indicate that inoperable status of safety systems (e.g.,
essential ventilation) be at the system level and the alarms did not assure operators that the system was operable.
The doors have self-closing devices and personnel are instructed not to prop the doors open. For these reasons, no unreviewed safety question was introduced.
(116)
Description of Change Section 13.5 of the FSAR was revised to incorporate reference to CE Standard Technical Specifications in relation to the fire protection program. This change was incorporated in Amendment 17 to the FSAR.
I. -
Summary of Safety Evaluation This change was administrative in nature.
CE Standard Technical Specifications were referenced in the FSAR so that the specific fire protection requirements could be deleted from PVNGS Technical Specifications.
Since the two Technical Specifications describe the same program, this cuange did not affect the fire protection program at all. Therefore, no unreviewed safety question was involved.
(117)
Description of Change This change involved replacing valve 13JCDNPDV0195 in the Condensate System with a Vanessa valie with a Bettis model T416M4 actuator.
The change affected FSAR Figure 10.4-9 and was implemented in PVNGS Units 1 and 2 during this reporting period.
Summary of Safety Evaluation The old masoneilan valve was found to be inadequate to sustain operation of the units, failing three times during the first 18 months of operation in Unit 1 and twice during the first year of operation in Unit 2.
The new Vanessa valve installs into the existing plant instrumentation and controls system and is operated in an identical manner to the old valve.
(118)
Description of Change This change involved installing a vent line, with isolation valve, from the existing plugged vent port on the charging pump suction stabilizers to the charging pump gas vent system. The change affected FSAR Figure 9.3-13 and was implemented in PVNGS Units 1 and 2 during this reporting period.
Summary of Safety Evaluation This modification was to permit venting of the charging pump suction pulsation dampener vessel to preclude one mechanism of gas binding of the charging pumps.
(119)
Description of Change This change involved installing a five gallon condensate pot on the holdup tank sample line (CH-N-351-HCDB-1/2") located in the 88' pipe chase. There will be a valve available for drainage into a container that will be removed and properly disposed of, via the RD system.
The change affected FSAR Figure 9.3-13 and was implemented in PVNGS Units 1 and 2 during this reporting period. - -
Summary of Safety Evaluation This modification was necessary to remove moisture from the holdup tank sample line, which ensures reliable and accurate sampling of the holdup tank as required by Technical Specification 3.3.3.9 and 3.11.2.5.
The modification received an adequate seismic analysis and will improve the reliability of the sampling.
(120)
Description of Change This change involved installing a 20 gallon condensate pot on the gas stripper H2 sample line (CH-N-324-HCDB-1"),
located in the gas stripper room.
A drain valve to be operated via a reach rod was included.
The change affected FSAR Figure 9.3-13 and was implemented in PVNGS Units 1 and 2 during this reporting period.
Summary of Safety Evaluation This modification was necessary to remove moisture from the gas stripper sample line, which ensures reliable and accurate sampling of the gas stripper as required by Technical Specification 3.3.3.9 and 3.11.2.5.
The modification received an adequate seismic analysis and will improve the reliability of the sampling.
(121)
Description of Change This change involved the installation of an in-line electromagnetic flowmeter and flow' rate /totalization panel in the Control Building on the domestic water distribution header to each unit.
The change affected FSAR Figure 9.2-6 and drawing 13-J-ZJF-002, Rev. 6, which is incorporated into the FSAR by reference.
This change was implemented in PVNGS Units 1 and 2 during this reporting period.
Summary of Safety Evaluation This modification provides a means for accurately determining the domestic water requirement for the unit distribution system at the control building.
The donestic water system is not included in any FSAR accident analyses.
(122)
Description of Change This change involved deleting the NPSH trip instrumentation from the Heater Drain Pump control circuits, and labeling them as " abandoned in place".
The change affected FSAR Figure 10.2-2 and was implemented in PVNGS Units 1 and 2 during this reporting period.
Summary of Safety Evaluation i
The NPSH trip devices provide a (au ect trip of the Heater Drain Pumps on degraded NPSH conditions.
However, the instruments have not proven to be reliable, based on monitoring the contact status during normal plant operation.
The existing FSAR' accident analyses address any potential malfunctions of the Heater Drain Pumps. -
a (123)
Description of Change This change involved rerouting the blowdown heat exchanger outlet flow from the heater drain pump suction to the main feedwater pump suction.
The change affected FSAR Figures 10.2-2 and 10.4-8 and was implemented in PVNGS Units 1 and 2 during this reporting period.
Summary of Safety Evaluation This modification was necessary to prevent component damage from water hammer action on the Heater Drain tank piping.
The existing FSAR accident analyses address any potential malfunctions of the Heater Drain Pumps.
(124)
Description of Change This change involved:
1.
Revamping the level control stations on the north end of feedwater heaters 3A, 3B, and 3C to physically raise the high level controllers, high and hi hi level alarms, and level gauges four inches from their existing positions.
2.
Removing the reset function in the normal level controllers EDN-LC-301, 302, and 303.
3.
Installing additional level gauges, 14 inches in span, in parallel with the normal level controllers EDN-LC-301, 302, and 303.
These changes tad FSAR Figure 10.2-2 and were implemented in PVNGS Units 1 at.; e auring this reporting period.
Summary of Safety Evaluation This modification was necessary to correct operational problems associated with feedwater heaters 3A, 3B, and 3C cascading drain flows, and the inability to maintain design values for the drain cooler approach.
Any potential malfunctions resulting from this modification are bounded by the " Loss of Normal Feedwater" accident analysis in the FSAR.
(125)
Description of Change This change involved adding an isolation valve for a pressure point on the remote shutdown room halon storage cylinders. The change affected FSAR Figure 9.5-1 and was implemented in PVNGS Units 1 and 2 during this reporting period.
I Summary of Safety Evaluation This modification was necessary to provide a pressure test point on the remote shutdown room halon shortage. cylinders for Technical Specification required surveillance testing.
The function on the i
halon storage cylinders is not altered by this modification.
i (126)
Description of Change This change involved installing HPS lighting in the condensate 1
transfer pump house vestibule and the essential spray pond pump house fan A and B air inlet enclosure.
The change affected Drawing j
13-E-ZYU-034:
Rev.
6, which is incorporated into the FSAR by reference. This change was implemented in PVNGS Units 1 and 2 during_
j this reporting period.
P Summary of Safety Evaluation This modification was necessary to illuminate the above described areas to be in compliance with 10CFR73.46 and eliminate the use of compensatory measures such as portable lighting and security foot patrols.
(127)
Description of Change i
j This change involved increasing feeder cable size and rerouting cable to voltage regulators EQMAV31 and EQMBV30.
The change affected i
Drawings 13-E-PHA-001, Rev. 15, 13-E-PHA-002, Rev. 15, 13-E-PHA-007, Rev.
8, 13-E-PHA-008, Rev.
10, 13-E-ZAC-070, Rev.
24, and 13-E-ZAC-071, Rev.
18, which are incorporated into the FSAR by i
reference.
These changes were implemented in PVNGS Units 1 and 2 during this reporting period.
1 Summary of Safety Evaluation 4
i j
This change was necessary to assure the continued health and safety of personnel working it PVNGS. Operation exceeded cable design ampacity, causing excessive heat which expedites the insulation aging process.
Continued operation without the modification would have resulted in
}
equipment and personnel hazards.
Systems design and operation were not altered.
(128)
Description of Change, This change involved reworking the main steam lead -drains by cutting l
the steam lead drain pipes downstream of the current isolation valves i
and installing a second isolation valve, followed by a blank flange, in each line.
In addition, new valves wera installed in the drip pan drain lines above the tee where the steam drains joined.
The change affected FSAR Figure 10.3-1 and was implemented in PVNGS Units 1 and 2 l
during this reporting period.
i I
Summary of Safety Evaluation This modification was necessary to alleviate the main steam lead drain line from backing up to the safety valve drip pans.
The drip pans were overflowing, wetting pipe insulation and other equipment, creating a personnel safety hazard.
Piping failure probabilities were not increased since dead weight and dynamic loads were considered and accounted for in the modification.
(129)
Description of Change This change involved replacing the radiation monitor RU-l outlet solenoid isolation valve with a manual ball isolation valve.
The change affected FSAR Section 11.5.2.1.3.13, which stated the isolation valve automatically shut.
With the manual valve, this is no longer the case. This change was implemented in PVNGS Units 1 and 2 during this reporting period.
Summary of Safety Evaluation This modification was necessary to reduce. the amount of containment atmosphere leakage into the auxiliary building during maintenance on radiation monitor RU-1, to be within the airborne radioactive concentration limits of 10CFR20.103b(1). Credit is not taken for this valve in any FSAR safety analyses.
The setpoint for closure of this valve is 4-6 psig, where the setpoint for the safety related CIAS valves is 3.2 psig.
(130)
Description of Change This change involved adding a 20 minute timer to delay the automatic N2 dilution that occurs on a Hi Hi 02 concentration sensed by the 02 analyzers.
In addition, pressure reliefs were installed to allow a sample flow path to clear the system of the Hi Hi 02 signal.
Sample return lines were separated to prevent H2 and 02 mixing.
The change affected descriptions of these systems in FSAR Sections 9.3.2.3.7 and 11.3.1.1.6.
This change was implemented in PVNGS Units 1 and 2 during this reporting period.
Summary of Safety Evaluation This modification was necessary because the spurious spikes in the 02 analyzer were causing unnecessary N2 dilution, with no way to clear the system of the Hi Hi 02 signal.
In addition, the sample return lines had the potential for mixing of H2 and 0.
The time 2
delay does not prevent the dilution, but only delays it in order to manually clear the Hi Hi 02 signal.
This results in a reduced amount of gaseous radwaste being produced and will allow for a more efficient processing of the waste gas.
This modification does not change the operation of the analyzers, nor does it change any assumptions made in the FSAR accident analyses.
(131)
Description of Change A temporary modification was initiated in PVNGS Units 1 and 2 to install a 60 inch blind flange on the discharge bell of the CEDM normal ACU A fan (1MHCNA02A) which failed.
This change affected FSAR Figure 9.4-12.
Summary of Safety Evaluation This modification was to provide CEDM cooling in the event of CEDM normal ACU B failure.
CEDM ACU operation is not required for safe shutdown and has no safety related function.
(132)
Description of Change A temporary modification was initiated in PVNGS Units 1 and 2 to install a blind flange at dampers 1,2MHJBM01 and 1,2MHJAM52 to provide isolation between control room "B"
essential HVAC and control room normal AHU 1,2HJNA02.
This change affected the description of the normal control room HVAC in FSAR Section 9.4.1.2.2, the description of the essential control room HVAC in FSAR Section 6.4.2.2.2.J and FSAR Figure 9.4-1.
Summary of Safety Evaluation This modification was made to support bubbletight damper inspection of dampers 1,2MHJAM52 and 1,2MHJBM01.
The essential HVAC system retained all operational capabilities to fulfill the safety design bases.
The blind flanges were designed seismic category I to preclude the failure of other important to safety components.
(133)
Description of Change A temporary modification was initiated in PVNGS Units 1 and 2 to install blind flanges at the following locations:
1.
On the control room side of fire dampers 1,2MHJBM25.
2.
On the flanged connection above duct heater lEHJNE07 and the flanged connection below duct heater 2EHJNE09.
3.
On duct piece 12 in lieu of the volume damper.
These blanks provide isolation between control room and both the "B" train essential AFU and control room normal AHU. The changes affected descriptions in FSAR Sections 9.4.1.2.2, 6.4.2.2.2 A through G,
6.4.3.2, and 6.4.2.4.
Also affected was FSAR Figure 9.4-1.
l Summary of Safety Evaluation These changes were made to support reinstallation and inspection of bubbletight dampers 1,2MHJBM01, 1,2MHJBM55, 1,2MHJAM01, and 1,2MHJBM01.
The continued operability of the "A"
train AFU and the design of the blind flanges to seismic category I preclude the possibility of accidents not previously evaluated in the FSAR.
The blind flanges provide adequate control area isolation in place of bubbletight dampers.
Essential AFU HJAF04 functioned as designed to fulfill control room habitability requirements.
(134)
Description of Change A temporary modification was initiated in PVNGS Units 1 and 2 to install a special damper linkage arm to hold dampers 1,2MHJBM67 closed when the damper operator is in the failed (open) state. This affected FSAR Sections 9.4.1 and 6.4.2.4, and FSAR Figure 9.4-1.
Summary of Safety Evaluation This modification was made to maintain the damper in the closed position to provide a temporary control room pressure boundary.
Dampera 1,2MHJBM67 are maintained in the fully closed position, providing adequate control area isolation.
Essential AFU HJAF04 will function as designed to fulfill control room habitability requirements.
(135)
Description of Change A temporary modification was initiated in PVNGS Unit 2 to add a 1/2 inch plug threaded onto the outlet of the rupture disc body in the low pressure N2 system. This change affected FSAR Figure 9.3-14.
Summary of Safety Evaluation This modification was necessary to maintain operation of the low pressure N2 system while a replacement rupture disc was ordered.
The rupture disc was ruptured and the modification was to prevent N2 from blowing out the rupture disc opening, allowing system pressure to be maintained.
Pressure relief protection is provided by a
permanently installed relief valve with a setpoint of 125 psig.
Normal N2 pressure is 100 psig.
(136)
Description of Change A temporary modification was initiated in PVNGS Unit 1 to install stainless steel tubing jumpers in place of flow gauges in the seal water supply lines to the LRS evaporator pumps.
This change affected FSAR Figure 11.2-2.
Summary of Safety Evaluation This modification did not pose a safety concern since the tubing jumpers were of the same material as the remainder of the tubing in the lines. The pressure boundary integrity was not compromised.
(137)
Description of Change A temporary modification was initiated in PVNGS Unit 1 to provide breathing air to the containment for the March 1986 outage.
The breathing air system was composed of an Atlas Copco ZT3 oil-free rotary compressor, an Atlas Copco 1000 cfm water-cooled aftercooler, a 1500 gallon ASME air receiver, and an Arrow 3519 air dryer, all located in the yard area.
The equipment supplied air to the containment through three inch air hose headers at IIRT penetration
- 58 and all electrical power requirements were supplied by existing construction power. This change affected FSAR Figure 9.2-8.
Summary of Safety Evaluation The breathing air system was used during an outage in Modes 5 and 6, and would not impact any other plant systems.
(138)
Description of Change A temporary modification was initiated in Unit 1 to add a telephone to the Assistant Shift Supervisor desk in the control room.
The change affected Drawing 13-E-2JL-004, which is incorporated into the FSAR by reference.
Summary of Safety Evaluation The telephone system is not important to safety.
The telephone will be located on a desk well away from the control panels.
(139)
Description of Change A temporary modification was initiated in PVNGS Unit 1 to install a perforated sheet in the flanged connection above duct heater 1E-HJN-E04. This change affected FSAR Figure 9.4-1.
Summary of Safety Evaluation This change was necessary to eliminate excessive noise generated at the ceiling diffuser in the Shift Supervisors office, due to a high differential pressure across the balancing damper.
(140)
Description of Change This temporary modification was initiated in PVNGS Unit 1 to route a fire protection header to the ASME trailer located on the 176 foot elevation of the Turbine Building.
Hose station #8 had a tee installed so that piping could be routed to the trailer, as well as having sprinklers installed. This change affected FSAR Figure 9.5-1.
Summary of Safety Evaluation The addition of sprinklers to the ASME trailer will prevent the spread of fire. The interface with hose station #80 will not create any new accident conditions.
(141)
Description of Change This temporary modification was initiated in PVNGS Unit 2 to replace a six inch globe valve used to fill the CD/FW systems and to pressurize them prior to initiation of flow from the CD pumps, with a two inch globe valve. This change affected FSAR Figure 10.4-9.
Summary of Safety Evaluation This modification was made because the six inch valves experienced numerous failures of packing, and mechanical problems.
The valve being installed does not affect the operation of the system or its ability to perform its required tasks.
The valve is only used to put the system into operation and can fail in any position without negative.effect.
j (142)
Description of Change This temporary modification was initiated in PVNGS Unit 2 to install discharge pressure gauges to vent points on the charging pumps to determine pressure loss when the pumps are not running.
This change affected FSAR Figure 9.3-13.
Summary of Safety Evaluation The pressure gauges were added to existing vent connections.
The pressure gauge mass is not great and the vent points are designed to handle this weight, similar to designated pressure test points.
(143)
Description of Change A temporary modification was initiated in PVNGS Unit 1 to remotely monitor main feedwater pipe whip restraints 802, 803, 804 and 805.
This change involved installing LVDTS and thermocouples at the pipe whip restraints, and routing cables via scanners through electrical penetrations 87 and 91 to the temporary auto data computer.
The change affected Drawings 13-E-ZAC-065 and 13-E-ZAC-066, which are incorporated into the FSAR by reference.
Summary of Safety Evaluation Containment integrity was ensured since existing electrical penetrations were used.
Power supply for the equipment was non-class. The equipment, location, and installation was such that no existing FSAR accident analyses were affected.
i
(144)
Description of Change A temporary modification was initiated in PVNGS Unit 1 to maintain an operable TDAS system following close-out of the temporary procedure which installed the TDAS data acquisition points for power ascension.
This involved the addition of wiring between the terminals and data points.
The change affected Drawing 13-J-ZJF-009, which is incorporated into the FSAR by reference.
Summary of Safety Evaluation The modification only affects non-class instrumentation so the probability of an accident or malfunction of equipment important to safety would not be increased.
In addition, no new accidents would be created.
(145)
Description of Change I
This temporary modification was initiated in PVNGS Unit 1 to install a one inch socket weld globe valve in the vertical run of pipe just downstream of valve SG-V140, to stop leakage past valve SG-V140.
This change affected FSAR Figure 10.3-1.
Summary of Safety Evaluation The addition of the second isolation valve prevented leakage past SG-V140, preventing condensate from backing up to the seat of the safety valves, allowing the system to operate as designed.
(146)
Description of Change This temporary modification was initiated in PVNGS Unit 2 to install a digital storage recorder to monitor trip contacts to determine the cause of spurious actuations of reactor trip switchgear channel C.
The change affected Drawing 13-E-SBB-002, which is incorporated into the FSAR by reference.
Summary of Safety Evaluation l
The test equipment was electrically isolated by an isolation transformer on the primary side and by an isolation amplifier on the secondary side. The reactor trip switchgear will function as designed.
(147)
Description of Change For the auxiliary feedwater system, the nuclear sampling system, and the containment building HVAC system, several 1500 ohm resistors were replaced with 2000 ohm resistors in various motor control centers and auxiliary relay cabinets.
This modification affected several electrical diagrams that were incorporated by reference into the FSAR.
This change was impicmented in PVNGS Unit 1 during this reporting period.. -.
Summary of Safety Evaluation The replacement of the resistors was made in order to limit the current in various indicating lamps to values that are within the manufacturer's ratings.
This modification will prevent indicating lamps from burning out as quickly and will not have any impact on plant safety.
l (148)
Description of Change For the two safety-grade auxiliary feedwater
- pumps, the flow indicators (AFN-FI-015 and 026) on the full-flow recirculation lines were removed.
This modification affected FSAR Figure 10.4-11 and was implemented in PVNGS Unit i during this reporting period.
Summary of Safety Evaluation This modification does not effect the function of the auxiliary feedwater system and has no effect on any margins of safety.
These flow indicators were installed in the full-flow recirculation lines that are used for pump testing.
These lines are normally isolated by flanges during power operations and are only used during routine pump testing.
The flow indicators were local flow indicators that performed no safety function.
(149)
Description of Change
.t For various pumps in the reactor coolant system, auxiliary feedwater system, turbine cooling water system, plant cooling water system, extraction steam system, nuclear cooling water system, essential cooling water system, spray pond system, and safety injection system the thyrector diodes in the indication circuits of the motor space heaters were replaced with adjustable resistors. This change affected Drawing 13-E-PHB-005 which is incorporated by reference into the FSAR.
The change was implemented in PVNGS Unit i during this 3
reporting period.
Summary of Safety Evaluation This modification did not impact plant safety.
The change corrects the condition of having the space heater for a pump energized while indicating an inoperable status (by the neon lamp being extinguished).
Failure of the new space heater indicating circuit with adjustable resistors has no impact on pump motor function.
(150)
Description of Change For the downcomer facedwater isolation valves (SGA-UV-172 and 175 SGB-UV-130 and 135), the air booster assembly was deleted and the l
service gas system was modified to supply 240 psi nitrogen gas directly to the valve operators.
This change affected FSAR Figure 10.3-1 and was implemented in PVNGS Unit i during this reporting period.
I l -
Summary of Safety Evaluation The previous air boosters on the downcomer feedwater isolation valves were unable to furnish the 240 psi pressure required to properly operate the valves.
This modification removed the air boosters from the valves and supplied the valve actuators with 240 psi nitrogen gas from the service gas system.
This modification ensured proper operation of the valve and did not increase the probability of occurrence or the consequences of any accidents previously evaluated in the FSAR.
(151)
Description of Change The auxiliary steam system was modified to provide a steam supply line to the existing decontamination spray booth in the radwaste building.
This modification affected FSAR Figure 10.3-2 and was implemented in FSAR Unit 1 during this reporting period.
Summary of Safety Evaluation The steam supply line is required for steam cleaning in the decontamination spray booth.
This modification to suppy auxiliary steam to the decontamination spray booth had no impact on nuclear safety at PVNGS and did not involve an unreviewed safety question.
(152)
Description of Change The main control board handswitch for valve CH-250 was removed from the control board.
This modification affected FSAR Figure 9.3-13 and was implemented in PVNGS Unit i during this reporting period.
Summary of Safety Evaluation Valve CH-250 in the chemical and volume control system is associated with the crud system which has been isolated and is no longer in use.
This valve has a handswitch and control board mimic on panel B03 of the main control board.
Due to the proximity of this handswitch with other important controls on the main control board, this handswitch was removed in order to avoid operator confusion.
The removal of this handswitch did not impact plant safety since the subsystem associated with this valve is no longer in use.
(153)
Description of Change For the chemical and volume control system, local level indicators were installed for the refueling water tank and the reactor makeup water tank.
This modification was implemented in PVNGS Unit 1 during this reporting period and affected FSAR Figure 9.3-13.
Summary cf Safety Evaluation This change to add local level indication for the refueling water tank and the reactor makeup water tank provides the capability to obtain level information locally (at the tank) in the event of a control room fire where the remote level indication is lost.
This modification improves plant safety by providing additional capabilities for mitigating a control room fire event.
(154)
Description of Change For the chemical and volume control system charging pumps, drain lines were added to route the charging pump plunger well drains to a new charging pump oil drain tank.
This change affected FSAR Figures 9.3-13 and 9.3-6 and was implemented in PVNGS Units 1 and 2 during this reporting period.
Summary of Safety Evaluation The previous design routed the charging pump plunger well drains directly to the liquid radwaste system which is not designed to process oil.
This change will increase the reliability and safety of the liquid radwaste system by significantly reducing the amount of oil introduced into the system.
(155)
Description of Change For the pressurizer spray valves of the reactor coolant system, manual isolation valves were installed in the seal leakoff lines for the valves.
This modification affected FSAR Figure 5.1-1 and was implemented in PVNGS Units 1 and 2 during this reporting period.
Summary of Safety Evaluation The installation of the manual isolation valves on the seal leakoff lines for the main pressurizer spray valves provides for personnel safety during maintenance activities on the valves.
Since the two pressurizer spray valves share a common seal leakoff return header, the manual isolation valve was necessary in order to isolate the operable valve from the valve that is being worked on.
(156)
Description of Change In order to prevent inadvertent operation of valve CHA-HV-524, the valve was locked open with the power supply removed.
The power supply for the valve position indication was modified to ensure that control room position indication is maintained when the valve power supply is removed.
This modification affected FSAR Figure 9.3-13 and was implemented in PVNGS Unita 1 and 2 during this reporting period.
i )
Summary of Safety Evaluation 1
This modification provided an alternate power supply to ensure that valve position indication is available in the control room at all times as required by Regulatory Guide 1.141 for all power operated containment isolation valves.
Valve CHA-HV-524 was locked open with power removed in order to ensure that the auxiliary pressurizer spray flow path remains available.
(157)
Description of Change A flow orifice (F0-272) was installed in the common discharge header from the chemical and volume control system holdup pumps.
This modification affected FSAR Figure 9.3-13 and was implemented in PVNGS Unit 1 during this reporting period.
Summary of Safety Evaluation The flow restricting orifice was lastalled in the discharge line from the holdup pumps to prevent pump runout conditions when the holdup pumps are lined up to discharge through the reactor drain filter.
The change enhances the operation of the holdup pumps and has no adverse impact on plant safety.
l (158)
Description of Change For the diesel generator jacket water cooling system, test connections with drain isolation valves were installed between check valves V002 and V003 and between check valves V011 and V012.
This modification affected FSAR Figure 9.5-9 and was implemented in PVNGS Units 1 and 2 during this reporting period.
Summary of Safety Evaluation The addition of test connections with drain isolation valves between two sets of check valves does not affect the function or the operation of the diesel generator jacket water cooling system.
This modification will facilitate the performance of inservice testing of the check valves.
(159)
Description of Change In the condensate system, seal water was piped to valve CDN-HCV-155.
l This modification affected FSAR Figure 10.4-9 and was implemented in PVNGS Unit 1 during this reporting period.
Summary of Safety Evaluation i
Seal water is now supplied to the leak off connection for valve CDN-HCV-155 in order to prevent a loss of condenser vacuum in the event of valve stem leakage.
This modification does not impact nuclear safety at PVNGS.
1.-
(160)
Description of Change Turbine trip drain lines SGN-162-DBDB-4 and SGN-165-DBDB-4 and steam trap drain line SGN-155-DBDB-2 were re-routed to dump directly into the main condenser.
This modification affected FSAR Figures 10.4-9, 10.2-2, and 10.3-1 and was implemented in PVNGS Units 1 and 2 during i
this reporting period.
Summary of Safety Evaluation The previous system design had these drain lines dumping into the j
heater drain tank high level dump lines.
The problem with this previous design was that when the turbine was at 0% power conditions a potential for water hammer existed due to the mixing of cold condensate water with the steam from the drain lines.
Thus, the modification eliminated the potential for having a water hammer event on the secondary side of the plant.
(161)
Description of Change i
For the heater drain pumps, the mechanical seal injection lines, vent and drain lines, and stuffing box cooling water supply and return lines were re-routed.
This modification affected FSAR Figure 10.2-2 and was implemented in PVNGS Unit i during this reporting period.
Summary of Safety Evaluation I
The purpose of this modification was to correct the routing /
i arrangement of the seal water supply piping to the heater drain pumps I
in order to make the pump function as originally designed.
The modification had no impact on the safety of the plant.
I (162)
Description of Change Two portable fire extinguishers were installed in the decontamination i
and laundry facility.
This modification affected section 9B.2.20 of I
the FSAR and was implemented in PVNGS Unit i during this reporting j
period.
l Summary of Safety Evaluation l
The installation of the portable fire extinguishers will provide for better fire protection in the decontamination and laundry facility.
The charge does not decrease the safety of the facility.
(163)
Doncription of Change Differential pressure indicators were installed across the suction strainers of the main feedwater pumps.
This modification affected i
FSAR Figure 10.4-10 and was implemented in PVNGS Unit 1 during this reporting period.
~
j Summary of Safety Evaluation Installation of the pressure differential indicators will improve the operation of the feedwater system by allowing the operators to monitor the differential pressure across the feedwater pump suction strainers. This change should ensure that the system is operated in a correct manner.
1' (164)
Description of Change i
For the gaseous radwaste system, a 1-inch manual valve was installed on the gaseous radwaste discharge line.
This change affected FSAR Figure 11.3-2 and was implemented in PVNGS Units 1 and 2 during this reporting period.
4 Summary of Safety Evaluation
)
The new 1-inch valve was installed where an existing welded pipe cap 1
was located.
The installation of the new valve is an operational convenience that allows for an in-line calibration capability for flow element FE-33.
l (165)
Description of Change A flow switch was installed to sense air flow in the hot deck ductwork of access control area Air llandling Unit (AllU) IIAN-A02.
Thia l
modification affected FSAR Figure 9.4-3 and was implemented in PVNGS Unit 1 during this reporting period.
i Summary of Safety Evaluation During day time operation of the access control room AHU during the summer months, full cooling is required and air flow is shut off to l
the hot deck.
This results in the controller demanding full heat output from the heaters and results in the heaters tripping. A manual j
reset of the heaters is required before they can operate again and
{
this manual reset is not easily accessible.
The newly installed flow switch eliminates this continual tripping and resetting of the heaters. The change is in a non-safety related ilVAC system and had no j
effect on safety.
(166)
Description of Change i
I For the control building battery room ventilation fans, the control i
circuit was modified to provide power to the seal in fan running contact from the remote control power circuit fuse instead of the safe shutdown fuse.
This change affected Figure 13-E-IlJ B-023 which in incorporated by reference into the FSAR.
The change was implemented in PVNGS Unit i during this reporting period.
1 l
j i
F Summary of Safety Evaluation 1
This change to power the seal in relay contact from the remote control power circuit instead of the safe shutdown circuit will ensure that the main control room isolation switch is operable before a ground fault blows the safe shutdown control fuse.
The change serves to increase the reliability of the control circuitry and does not involve i
an unreviewed safety question.
s (167)
Description of Change For the two radwaste building Air Handling Units (AHUs), differential pressure switches were installed across the OIC air filters.
This j
modification affected FSAR Figure 9.4-5 and was implemented in PVNGS Unit 1 during this reporting period.
Summary of Safety Evaluation j
The addition of the differential pressure switches across the OIC filters of the radwaste building AHUs will allow for more efficient i
operation of the AHUs.
The differential pressure switches are interlocked with the drive motor for the OIC filters to rotate the i
filter when the differential pressure indicates that there is a i
aufficient dust load on the f11ter.
The change promotes increased filter efficiency and does not impact plant safety.
I (168)
Description of Change l
For the two radwaste building AHUs, the existing 011 Impingement Cleaner (OIC) timers were replaced with better quality timers.
This modification affected FSAR Figure 9.4-5 and was implemented in PVNGS Unit 1 during this reporting period.
Summary of Safety Evaluation By changing out the timer with a better quality timer, the OIC filter can be made to operate as intended and the rate of filter travel can be adjusted to permit the filter media to accumulate sufficient dust which will minimize the amount of oil carried away by the alc stream.
The change makes the OIC filters operate as intem ed and does not involve an unreviewed safety question.
(169)
Dencription of Chango Pressure test points were installed on the evaporator vapor body of the liquid radwaste system evaporator.
This modification affected FSAR Figure 11.2-2 and was implemented in PVNGS Unit 1 during this reporting period.
Summary of Safety Evaluation i
The change to add the pressure test points to the evaporator vapor i
1 body allows for the measurement of pressure drop across the vapor body reflux trays.
The change was made to allow additional monitoring of l
the equipment and does not affect nucient safety at PVNGS. - - - - - -
i i
(170)
Description of Change Flowmeters and throttle valves were installed in the seal water lines for the liquid radwaste system evaporator main recirculation pump, i
concentrate monitor pumps, and evaporator concentrate pumps.
The change affected FSAR Figures 11.2-2 and was implemented in PVNGS Unit 1 during this reporting period.
Summary of Safety Evaluation The addition of the flowmeters and throttle valves in the seal water lines for these liquid radwaste system pumps will allow the operators to throttle seal water flow to the pumps. This will allow for control of the amount of water being dumped into the radioactive drain system.
(171)
Description of Change The air supply lines to the turbine front standard were changed from hard pipes to flexible hoses.
This change affected FSAR Figure 10.2-1 and was completed in PVNOS Unit 1 during this reporting period.
Summary of Safety Evaluation The installation of the flexible hoses on the air lines to the turbine front standard will eliminate an over-stressed condition and will l
allow for unrestricted thermal expansion of the turbine and front standard.
The change eliminates a potential problem and does not involve an unreviewed safety question.
(172)
Description of Change 4
Valves attached to the ASME test points of the main steam lines were removed and the pipe caps were seal welded at the test points.
This 4
change affected FSAR Figure 10.2-1 and was completed in PVNGS Unita 1 and 2 during this reporting period.
Summary of Safety Evaluation The previous lines to the ASME test points experienced a fatique due to vibration.
Removal of the valves and capping the lines close to the steam line will reduce the probability of a steam leak caused by fatique of the lines.
(173)
Dencription of Change
]!
[
The control valve logic for the main turbino control valves was changed from full arc admission to partial are admission.
The modification af fected FSAR Figure 10.2-1 and was implemented in PVNGS Unit 1 during this reporting period.
f l
l i
l l
i
[
-sa-l i
J Summary of Safety Evaluation j
This modification was made to a non-safety related system and did not j
affect plant safety.
The change to partial are admission to the high pressure turbine results in a slight increase in gross output from the turbine / generator unit.
l (174)
Description of Change The normal water level setting and the high water level alarm setpoint for the spent fuel pool and the refueling pool were changed to 138 feet 1-inch and 138 feet 2-inches, respectively.
This change i
affected FSAR Section 9.1.3.3.1.1 and was implemented in PVNGS Unit 1
]
during this reporting period.
Summary of Safety Evaluation With the previous normal water level setting, the bottom of the
)
opening for the spent fuel pool liner plate is above the normal water I
level which prevents the pool skimmers from operating efficiently.
I Additionally, the opening of the new fuel elevator motor compartment l
1s at the same elevation as the previous high level alarm setpoint 1
which could have allowed water flow into the compartment and potentially damage equipment.
The new level setpoints will eliminate these problems and ensure proper operation of the fuel pool and assuciated equipment.
I (175)
Description of Change i
]
For the Class 1E electrical power distribution system, the load j
shedding of the Class 1E load centers was deleted and a load shedding j
contact was added in series with the liigh Pressure Safety injection
]
(IIPSI) pump motor 0.5 second sequencer contact in the starting circuit.
This change affected several electrical drawings which are l
incorporated by reference into the FSAR and this change was l
l implemented in PVNGS Unit 1 during this reporting period.
i Summary of Safety Evaluation i
1 This change was made to support an existing FSAR commitment discussed i
in FSAR Section 8.3.4.3.
This section requires that ECCS flow be i
i re-established within 13 seconds following a LOP.
The change to the l
ilPS1 motor starting circuit allows for the llPSI pumps to re-establish ECCS flow within 13 seconds.
l (176)
Dencription of Change Wall-mounted telephones were installed in the auxiliary building east and west penetration rooms and in the make-up pump room.
The i
installation of the phones af fected several auxiliary buiding conduit and tray plan drawings that are incorporated by reference into the FSAR.
This modification was completed in PVNGS Unit 1 during thia l
reporting period.
4 1 -
c Summary of Safety Evaluation 4
The installation of the wall-mounted telephones in several rooms of the auxiliary building will allow the operators to communicate while working inside these rooms.
The change does not involve an unreviewed safety question.
(177)
Description of Change This f acility modification involved the addition of 6 anode beds to restore cathodic protection around the diesel fuel oil tanks.
This change affected several underground electrical duct layout diagrams which are incorporated by reference into the FSAR.
The modification was impicmented in PVNGS Unit 1 during this reporting period.
I Summary of Safety Evaluation i
The additional anode beds will enhance the operation of the system and will not impact the FSAR safety analyses.
The modifications will increase the cathodic protection for components of the diesci fuel oil system.
(178)
Description of Change A smoke detector was added on the 140 foot lovel of the radwaste I
building.
This change affected the fire protection section of the FSAR and was implemented in PVNGS Units 1 and 2 during this reporting period.
Summary of Safety Evaluation The smoke detector was added due to the increased combustible loading in this area of the radwaste building that has been designated as the i
site of the radwaste volume reduction program.
The addition of the l
nmoke detector will increase plant safety by providing additional fire detection capabilities.
(179)
Dencription of Change The cold lab nink drains and the cold lab wet rack panel drains were re-routed to the chemical waste system.
This modification affected FSAR Figures 9.3-10, 9.3-6 and 9.3-3 and was impicmented in PVNGS Units 1 and 2 during this reporting period.
Summary of Safety Evaluation The previous system denign routed theno cold lab drains into the radioactive d rain nystem.
Thus, the liquid from the cold lab wan proccused by the liquid radwaste nystem which van very expensive due to the amount of water from this source.
The accondary sampic water will now be sent to the chemtent waste neutralizer tanks where it will be nampled prior to retcane to the onnite evaporattia pond.
=
(180)
Description of Change Flow signals for the plant vent, fuel building exhaust vent, and the condenser air removal exhaust vent were added as inputs to the Emergency Response Facilities Data Acquisition and Display System (ERFDADS).
This modification affected FSAR Section 11.5 and was j
implemented in PVNGS Unit 1 during this reporting period.
Summary of Safety Evaluation i
l Tue installation of flow sensors at the plant release points satisfies the requirements of ANSI N13.1-1969, Regulatory Guide 1.21, and Regulatory Guide 1.97.
The change allows for additional monitoring of 4
radioactive releases by allowing for monitoring of the discharge flow i
rates.
(181)
Description of Change
{
For the post accident sampling system, a new valve module, remote grab l
sampler, and switch box were installed.
This change affected various electrical diagrams which are incorporated by reference into the
{
FSAR. The change was completed in PVNGS Unit i during this reporting l
period.
l Summary of Safety Evaluation 1
These changes to the post accident sampling system were made in order j
to provide a pressurized and/or depressurized grab sample capability for obtaining samples from the reactor coolant
- system, safety injection system, or containment radwaste sump.
The change was required in order to meet the NUREG-0737 requirements.
(182)
Description of Change The domineralized water supply line to the secondary chemical control system chemical injection tanks was changed from a carbon steel pipe to a stainless stcol pipe.
This modification affected FSAR Figures 10.4-6 and 10.4-9 and was implemented in PVNGS Unit i during this reporting period.
Summary of Safety Evaluation 4
The previous piping was being deteriorated by demineralized water.
Replacement of the piping with stainless steel pipe prevents crud from 4
beina injected into the steam generators or from clogging drains and i
valves.
i (183)
Description of Chanan l
For the condenser hotwell and circulating water sample pumps, the previous diaphragm type metering pumps were replaced with contrifugal type pumps.
This modification affected FSAR Figure 9.3-3 and was implemented in PVNGS Unit i during this reporting period.
s I
Summary of Safety Evaluation The replacement of these secondary sample pumps did not involve an unreviewed safety question.
The previous diaphragm type metering pumps tended to pulsate badly, lose auction readily, and required frequent maintenance and repair.
The new centrifugal type pumps have proven operational experience in this application in other operating plants.
(184)
Description of Change For the condensate desineralizer package, the previous L&N sodium monitor was replaced with an Orion Sled sodium monitor.
This change affected FSAR Figure 10.4-7 and was implemented in PVNGS Unit 1 during this reporting period.
Summary of Safety Evaluation This change was made to eliminate a potential personnel ' safety hazard.
Specifically, the previous L&N sodium monitor required the use of a toxic and flammable dimethylamine gas which was used to adjust the sample pH.
The new sodium monitor does not require the use of this toxic gas so the new monitor eliminates the personnel safety hazard.
(185)
Description of Change For several Valcor and Target Rock solenoid valves, the wiring of the EFFDADS valve position signal was modified.
This modification affected several electrical diagrams that are incorporated by reference into the FSAR. The modification was completed in PVNGS Unit i during this reporting period.
Summary of Safety Evaluation The previous ERFDADS signal for these containment isolation valves were wired to the valve open limit switch.
This would only indicate if the valve was open or not open and did not allow for positive indication that the valve was clooed.
Therefore, the ERFDADS signal for valve position was changed to the close limit switch to provide indication as to whether the valves were closed or not closed.
This modification improved the monitoring of containment isolation valve position from the emergency response facilities.
(186)
Description of Change Control Room Essential Filtration Actuation Signal (CREFAS) inputs were added to the ERFDADS for use in the Safety Parameter Display System (SPDS) display.
The change af fected Drawing 13-E-SAB-002 which is incorporated by reference into the FSAR.
Additionally, the chango was incorporated in PVNGS Unita 1 and 2 during this reporting period. i
Summary of Safety Evaluation This modification did not involve an unreviewed safety question.
The change allows for additional monitoring of the status of the plant from the emergency response facilities.
Specifically, two spare i
Balance of Plant (BOP) ESFAS contacts were used as inputs to the ERFDADS on the status of CREFAS "A" and "B".
(187)
Description of Change The ERFDADS input for main turbine speed was changed from turbine speed pickup sensor #7 to turbine speed pickup sensor #6.
This modification affected several control building conduit and tray plan drawings which are incorporated by reference into the FSAR.
The modification was completed in PVNGS Unit I during this reporting period.
Summary of Safety Evaluation This change had no impact on plant safety. The previous turbine speed signal to ERFDADS from turbine speed pickup sensor #7 was a direct frequency signal that was not accepted by ERFDADS.
The new signal 3
from turbine speed pickup sensor #6 is compatible with ERFDADS since it is a 1-5 MA analog signal.
(
(188)
Daac rfiticn ef Chc...,s.
The existing air supply filter regulators for the Atmospheric Dump Valves (ADVs) were replaced with a new filter.
The modification af fected FSAR Figure 10.3-1 and was implemented in PVNGS Units 1 and 2 l
during this reporting period.
Summary of Safety Evaluation i
Operation of the ADVs was erratic due to the choked flow condition at I
the previous filter regulator for the valve positioner.
The replacement of the filter reguintor with a new filter will allow i
better flow of instrument air to the ADVs which will result in i
smoother operation of the valve positioner.
This design change i
enhanced plant safety by improving operation of the ADVs.
(189)
Dencription of Change i
For the main steam supply system, drain valves SGN-UV-31, 32, 33, 34, 35, 36, 37, and 30 were re-wired so that a turbine trip does not open these valves.
This change affected FSAR Figure 10.3-1 and was Implemented in PVNGS Unita 1 and 2 during this reporting period.
l I
1 I
i l 1 i
Summary of Safety Evaluation These drain valves are located downstream of the main steam isolation valves.
The previous system design had these drain valves opening upon a turbine trip which resulted in overcooling of the RCS.
The revised system design improves plant safety by eliminating the potential for RCS overcooling by ensuring that these drain valves do not open on turbine trip.
(190)
Description of Chanae The following globe valves in the Atmospheric Dump Valve (ADV) nitrogen supply system were replaced with packless globe valves:
SG-V341, V342, V343, V345, V336, V337, V338, V344, V362, V363
- V364, V365, V356, V354, V355 and V352.
This modification affected FSAR Figure 10.3-1 and was implemented in F"NGS Unit i during this reporting period.
Summary of Safety Evaluation The existing globe valves wore placed with packless globe valves to eliminate a continuous leakage of nitrogen gas from the ADV nitrogen accumulators.
The previous leakage was requiring the operators to charge the accumulators more frequently.
Implementation of this change improved plant safety and reduced the routine charging operations by reducing the ADV nitrogen accumulator leak rate.
(191)
Description of Change For the Main Steam Isolation Valves (MSIVs) and Feedwater Isolation Valves (FWIVs), test valves were installed in the instrument air line.
This change affected FSAR Figure 9.3-1A and.<ss implemented in PVNGS Unita 1 and 2 during this reporting period.
Summary of Safety Evaluation the test valves were installed in the instrument air supply lines to the MSIVs and FWIVs to allow for bleeding off the instrument air from the line to simulate a loss of instrument air supply. This allows for verification of the leak tightness of check valves in the air supply lines.
This will improve plant safety by providing the capability to test the check valves.
(192)
Description of Change The Safety Injection Tank (SIT) drain line tape were re-located closer to the first chock valve from the RCS on the cold leg safety injection lines.
This modification affected FSAR Figure 6.3-1 and was implemented in PVNGS Units 1 and 2 during this reporting period. -
Summary of Safety Evaluation The relocation of these lines closer to the first check valve from the RCS allows for an increase in the safety of the plant by providing a means to borate the cold leg injection lines approximately up to the check valves.
(193)
Description of Change The interlock circuit for the shutdown cooling suction isolation valves was modified so that the valves (SI-651 through 656) will fail as-is on a loss of power in the control power supply.
This change affected electrical drawings 13-E-SIB-013, 014 and 015 which are incorporated by reference into the FSAR.
Additionally, the modification was implemented in PVNGS Units 1 and 2 during this reporting period.
Suemary of Safety Evaluation With the previous design, tuo loss of power to the instrument cabinets having the interlock control modules could have caused the shutdown cooling suction isolation valves to close.
This could result in the loss of shutdown cooling and/or damage to the LPS1 pumps.
This modification ensures that the valves fail as-is on loss of the control power which ensures the continuance of shutdown cooling operation.
(194)
Desertption of Chanan Security barriers were upgraded and security hardware was revised.
The modifications affacted several auxiliary and control building conduit and tray plan drawings that are incorporated by reference in the FSAR.
The changes were implemented in PVNGS Unit i during this reporting period.
S_ummary of Safety Evaluation These changes were implemented to resolve NRC preoperation Security inspection findings and involved safeguards information.
(195)
Doncription of chanaa A totalising flowanter was installed in the hypochlorite supply line to the essentint spray ponds.
The modifications affected F8AR Figure 9.2-1 and was implemented in pVNGS Unit 1 during this reporting period.
Summary of Safety Evaluation This modification did not involve an unreviewed safety question.
The installation of the tota 11 sing flow motor will allow operations to measure the hypochlorite consumption of the essential spray ponds and will allow for accurate control of the hypochlorite additions. _. _
1 e
j (196)
Description of Change i
For the essential spray pond system, corrosion coupon racks were Installed in:
- 1) the line off the spray pond pump vent, and 2) the i
line off the spray pond filter pump discharge vent.
This addition affected FSAR Figure 9.2-1 and was implemented in PVNGS Unit i during this reporting period.
Summary of Safety Evaluation i
The installation of the corrosion test racks allows for monitoring the corrosive effects of the spray pond water on the cooling water piping
[
i and heat exchanger materials.
This will improve the safety of the j
plant by providing for a more timely identification of potential corrosion problems and corrective actions.
i t
j (197)
Description of Change Pressure gauges SPN-pI-216 and 217 were added on the spray pond header 1
at points where existing test points were.
This modification affected i
i FSAR Figure 9.2-1 and was implemented in PVNGS Unita 1 and 2 durinR l
this reporting period.
l Summary of Safety Evaluation I
j This modification will allow engineering personnel to periodically l
check the pressure in the main spray headers of the essential spray pond system.
The modification did not involve an unreviewed safety question.
l t
(198)
Doncription of chanan For thn radiation monitoring system, the " channel fail" contacts that j
initiate BOP ESFAS actuations have been removed for each of six l
radiation monitors.
This change affected FSAR Section 11.$.2.1.1.4 l
and was impicmented in PVNGS Unit 1 during this reporting period.
Summary of Safety Evaluation 1
i With the previous design, the radiation monitoring system had six j
monitors which provided trip signals to the 80P ESFAS upon the occurrence of either a
high radiation condition or equipment 5
failures.
Operating e portance has shown numerous 80P ESPAS
(
j acutations due to momentary channel fall signals being output from the
{
radiation monitors.
Thii plant change eliminated these unnecessary B0p KSFAS actuations by removing the channot fail inputs from the i
radiation monitors.
Tuo DOP E8FAS can still be actuated by high radiation signals from the radiation monitors or by manual actuation.
i
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r I
(199)
Description of Change For the solid radwaste system, a one inch globe valve was added to line SRN-064-HCDA-1 upstream of valve SRN-HV-346.
This change affected FSAR Figure 11.4-2 and was implemented in PVNGS Unit 1 during this reporting period.
Summary of Safety Evaluation The one inch globe valve will allow for throttling of SRN-P02 flush flowrata to 16 spa.
It is necessary to control the flowrate of the l
waste feed pump to 16 spa to obtain the required flow for i
solidification with no free-standing water.
(200)
Description of chanaa For the nuclear sampling system, power and control independent from the main control room was provided for valves SSA-UV-203 and i
SSB-UV-200 and a bypass was added to valve SSN-HV-015.
This change
{
affected FSAR Table 9.B.1-4 and was implemented in PVNGS Unit i during this reporting period.
I Summary of Safety Evaluation This modification did not involve an unreviewed safety question.
The l
change to the nuclear sampling system valves will allow for a RCS sample to be obtained for analysis in the event of a control room fire.
Thus, the change improves nuclear safety at PVNGS by providing this additional sampling capability.
l t
(201)
Description of channa A 208 volt receptacle was installed inside containment for the hydra-set precision load positioner control console.
This change
{
affected drawings 13-E-ZCC-017 and 018 which are incorporated by l
reference into the FSAR.
The change was implemented in PVNGS Unit 1 l
during this reporting period.
Summary of Safety Evaluation The installation of the additional receptacto did not involve an i
unreviewed safety question.
The permanent power source for tho hydra-set control console will provide for ease of operation.
(202)
Description of_ change
[
Threshold beras were installed at each of the main pressuriser spray valvo compartments and a drain line was installed to the floor drain syntes.
This modification affected FSAR Figure 9.3-4 and was i
isplemented in PVNGS Unit A during this reporting period.
i t I
Summary of Safety Evaluation The threshold beras were installed at each of the main pressurizer spray valve compartments in order to contain the leakage of water from the main pressurizer spray valves.
This eliminates widespread boric acid contamination due to leaking spray valves.
(203)
Description of change l
Five flow totalizers were installed in the lines to the onsite evaporation pond.
This modification affected FSAR Figures 9.3-10 and 10.4-4 and was implemented at PVNGS during this reporting period.
j Summary of Safety Evaluation 1
i The change will allow monitoring of the liquid discharge to the onsite evaporation pond.
The change did not involve an unreviewed safety 2
question.
i (204)
Description of Chanae
\\
Drain valves, a humidity sensor, and humidistat were installed for the l
Technical Support Center (TSC) Air Filtration Unit (AFU) and drain i
valves, fire protection to charcoal filters, a humidity sensor, and a humidistat were installed for the Emergency Operations Facility AFU.
i The changes affected FSAR Figure 9.5-1 and were implemented at PVNGS during this reporting period.
l Summary of Safety Evaluation l
The drain valves on the AFUs were required by ORNL-NSIC-65.
The I
humidity sensors and humidistata are required to regulate heater operation in order to control the humidity to within 70% for i
efficiency of the charcoal filters.
These changes ensure safe and I
officient operation of the TSC and EOF AFUs.
(205)
Description of chanac For the condenser air removat pumps, the thermostatic air vent device was removed and the air relief tube from the condenser air removal vacuum pump drain trap was capped.
This modification affected FSAR Figure 10.4-1 and was impicmented in PVNGS Unit 2 during this reporting period.
a Summary of Safety F. valuation i
This modification to the condenser air removat pumps was made to j
prevent air leakaan into the condenser and there was no effect on the r
j safety analyses.
Nor does removal of the thermostatic air vent introduce any new or diffarent kinds of accidents or malfunctions.
4 i
t a.
1 (206)
Description of Change For the condensate system, the existing condensate overboard valves were replaced with Fisher control valves and drain and isolation valves were added in the overboard lines.
This change affected FSAR Figure 10.4-9 and was implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation This change had no effect on nuclear safety at PVNGS.
The new condensate overboard control valves will provide for better control of the overboarding operation and the isolation valves will allow individual condensate overboard valves to be isolated for maintenance.
(207)
Description of Change Overvoltage protection relays were provided for solenoid valves CHN-PDY-240B and CHN-HY-239 in the charging header.
This change affected drawing 13-E-ZAC-073 which is incorporated by reference into the FSAR.
Additionally, this change was completed in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation The overvoltage protection isolation relays were provided for valves CilN-PDY-240B and CHN-HY-239 in order to ensure that these valves will close.
These two valves are the backpressure control valve and the charging header isolation valve (respectively) on the CVCS charging line to RCS loop 2A.
At least one of these valves must close in order to ensure auxiliary pressurizer spray capability when needed.
This modification helps to ensure that the valves vill close.
(208)
Description of Change For the CVCS charging pumps, a dedicated gas vent system was installed.
This modification affected FSAR Figure 9.3-13 and was implemented in PVNGS Unit 2 during this reporting period.
Sum 1ary of Safety Evaluation The gas vent system was installed to provide the capability to vent hydrogen gas from the charging pumps in the event that the pumps become gas bound on the Volume Control Tank (VCT) hydrogen cover gas.
The vent system vents the gas to a portion of the auxiliary building that receives casentini ventilation.
Thus, the gas vent system eliminates the potential for hydrogen explosions in the charging pump cubiclea which do not receive essential ventilation.
, l 1
(209)
Description of Change For the circulating water blowdown system, the existing single flow transmitter system was replaced with a dual flow transmitter system.
This change affected FSAR Figure 10.L-4 and was completed in PVNGS Unit 2 during this reportin;, period.
Summary of Safety Evaluation The above change had no effect on nuclear safety at PVNGS.
The previous single flow transmitter system did not have sufficient range to measure high range circulating water blowdown flow.
The addition of the second flow transmitter system will allow for the monitoring of blowdown flow from abnormally low to abnormally high rates of blowdown.
(210)
Description of Change For the circulating water system, drain valves were added to the condenser water box outlet legs on the cross-under loops and on the condenser shell "C" waterbox outlet legs.
This modification affected FSAR Figure 10.4-4 and was implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation The drain valves on the condenser water box outlet legs were added to allow for draining the waterbox legs to allow for maintenance activities when required.
This modification did not involve an unreviewed safety question and involved only non-safety related equipment.
(211)
Description of Change A 1-1/2 inch line was installed from the domestic water system to the emergency shower and eyewash station at the Spray Chemical Addition Tank (SCAT) room in the auxiliary building.
This modification affected FSAR Figure 9.2-6 and was implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation The previous design provided water to the emergency shower and eyewash i
station from a non-potable water source.
This modification corrects this deficiency by connecting the station to the domestic water system to meet Code and OSHA requirements.
(212)
Description of Change For the domestic water system, a backflow preventer was installed in place of valve VA37 and vacuum breakers were added by valves VA05, V992 V995, V993, V996, V994, and V997.
These modifications affected FSAR Figure 9.2-6 and were impicmented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation The backflow preventer was added in the domestic water supply line to the auxiliary boilers and the vacuum breakers were installed in other domestic water supply lines in order to prevent the potential for pollution of the domestic water system by back siphoning.
(213)
Description of Change For each train of the essential cooling water system, a test connection with a drain isolation valve was installed between the two check valves in the makeup line from the demineralized water system.
These modifications affected FSAR Figure 9.2-3 and were implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation Essential cooling water system check valves EWA-V018, EWA-V103, EWB-V029, and EWB-V077 are required to be tested periodically in accordance with ASME Section XI.
The addition of the test connections with drain valves between the two sets of check valves does not effect the system function and it facilitates the performance of inservice testing of the check valves.
(214)
Description of Change For main feedwater pump "B",
an adjustable time delay relay was installed in the pump control circuit for the low suction pressure trip. This change affected Drawing 13-E-FTB-006 which is incorporated by reference into the FSAR.
The change was implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation The addition of the time delay to the low suction pressure feedwater pump trip will reduce unnecessary plant down time caused by pump trips from normal operating transient conditions.
The time delay will allow the feedwater pump to remain operating through the short duration normal transients that cause a decrease in the feedwater pump suction pressure.
(215)
Description of Change Inputs to the plant computer were provided for five containment building air temperature inputs from thermocouples HCN-TE-42A, 42B, 42C, 42D, and 42E.
This modification affected FSAR Figure 9.4-12 and i
was implemented in PVNGS Unit 2 during this reporting period.
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_S_ummary of Safety Evaluation The addition of the containment air temperature inputs to the plant computer will allow for monitoring containment air temperature for fire detection.
The change did not involve an unreviewed safety question.
Isolation devices are included for the safety related inputs to the plant computer to prevent any adverse interactions.
(216)
Description of Change A time delay relay was added in the override circuit of dampers HJA-M02, M03 and IUB-M02, M03.
This modification affected drawing 13-E-lUB-024 which is incorporated by reference into the FSAR.
The change was implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation With the previous control circuit design for the dampers, the dampers failed to stay in the closed position when the SIAS or CREFAS signal was cleared due to a contact race condition.
The addition of the time delay relay in the override circuit will prevent opening of the damper before the ESFAS relays are reset.
This change to the override circuit will not prevent the dampers from performing their safety functions on receipt of a SIAS or CREFAS.
(217)
Description of Change Connectors and valves were installed on the containment hydrogen analyzer input lines to accommodate an air sampling bomb.
This modification affected FSAR Figure 6.2.5-1 and was completed in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation This change improves plant safety by providing a backup method for obtaining a containment air sample.
The change provides a means to obtain a containment air sample at the post-accident hydrogen analyzer by providing the appropriate valves and connections to accommodate a sampling bomb.
(216)
Description of Change For the radwaste building normal Air Handling Units (AHUs), the drain line from the air washer portion of the AHUs was re-routed from the roof scuppers to the control building west sump through the oily waste and non-radioactive waste system.
This modification affected FSAR Figures 9.4-5 and 9.3-11 and was implemented in PVNGS Unit 2 during this reporting period. m.
Summary of Safety Evaluation This modification re-routes the non-radioactive radwaste building AHUs air washer drain lines from the roof scupper to the control building sump in order to meet specific commitments made in the Environmental Report (ER).
The ER Sections 3.3.3 and 3.6.2 require the non-radioactive plant waste water be routed to the on-site evaporation pond. The waste water from the control building sump is routed to the evaporation pond.
(219)
Description of Change A 480V welding receptacle was installed on the south wall of the special bootie and storage area at the 140 foot level of the auxiliary building.
This change affected drawing 13-E-ZAC-025 which is incorporated by reference into the FSAR and the modification was implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation This modification did not involve an unreviewed safety question.
The new 480V welding receptacle will be used for providing power to a portable HEPA ventilation unit attached to the vacuum decontamination tent.
Without the new receptacle, power could have been provided to the HEPA unit by using an extension cord and passing the extension cord through fire doors which would have to be maintained open.
This would have necessitated the posting of fire watches.
(220)
Description of Change 120 VAC power was provided to the portal monitor, and two TLD readers in the auxiliary building.
This modification affected various auxiliary building conduit and tray plan drawings that are incorporated by reference into the FSAR. Additionally, the change was implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation This modification did not involve an unreviewed safety question.
The 120 VAC dedicated power supply was provided to the portal monitor and TLD reader to support permanent operation of this equipment.
(221)
Description of Change The existing manual transfer switches in vital inverters PNA-N11, PNB-N12, PNC-N13, and PND-N14 were replaced with static transfer switches.
This modification affected drawings 13-E-PNA-001 and 002 which are incorporated by reference into the FSAR and the change was implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation The previous manual transfer switch design resulted in s.!ow transfer ti.mes which resulted in the loss of some loads on the vital buses.
The replacement of the manual switch with a static transfer switch corrects this problem of loss of some loads.
Additionally, the addition of the automatic transfer switch does not alter the failure modes analysis because the transfer switch will not transfer to an out of tolerance supply.
(222)
Description of Change This change involved adding a mechanical shaft seal, with an external seal water supply, to the solid radwaste system waste feed pump (SRN-P02).
The change affected FSAR Figures 9.3-7 and 11.4-2 and was implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation This change was necessary since the current shaft packing gland was rapidly deteriorating by the abrasive liquid being processed.
The resulting radioactive leakage solidified on the pump bed plate and plugged the drainline.
Changes to the solid radwaste feed pump seals and the addition of seal water lines does not affect existing FSAR safety analyses.
(223)
Description of Change This change involved installing new raceways and cables, and a new distribution panel for the radiation monitoring system.
In addition, civil drawings and hanger details were changed to reflect as-built conditions for radiation monitoring instruments.
The change affected numerous drawings incorporated into the FSAR by reference.
This change was implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation The installation of a new distribution panel and new raceways and cables in the radiation monitoring system will not increase the probability of occurrence or the consequences of an accideat, nor will it create the potential of a new accident.
(224)
Description of Change This change involved routing flush water for the nuclear sampling system reactor coolant sample lines into the chemistry hot lab at the 140 foot elevation.
The change affected several drawings that are incorporated into the FSAR by reference.
This change was implemenred in PVNGS Unit 2 during this reporting period. --
Summary of Safety Evaluation This change was made to provide flush water to the reactor coolant sample line to be consistent with ALARA practices and reduce the potential for personnel radiation exposure.
The nuclear sampling system is a non-safety system and this change will not affect existing FSAR safety analyses.
(225)
Description of Change This change involved the installation of additional tees and valves in the nuclear sampling preparation panel, so that reactor coolant sample off-gas can be recirculated through the reactor coolant sample to scavenge additional dissolved gas.
The change affected FSAR Figure 9.3-2 and was implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation The method of obtaining a sample is not changed, rather, the method of analyzing a depressurized sample is modified to improve the accuracy of dissolved gas analysis.
This will enhance reactor system reliability through better chemistry control.
(226)
Description of Change This change involved revamping the 120 VAC power feeds for hotwell sample pumps SCN-P16A through F,
to eliminate excessive voltage drops. This change affected FSAR Figure 9.3-3 and was implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation The change improves the original design of the system.
Existing FSAR safety analyses are not affected.
(227)
Description of Change This change involved modifying the steam bypass control system auto nodulation sequence to result in a more even loading of the condenser shells and circulating water trains.
In addition, the " quick opening" and " quick opening permissive" signals are altered.
The change affected drawing 13-E-ZJC-009, which is incorporated into the FSAR by reference.
This change was implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation This change will only alter the sequence in which the valves open; the operation of the system is not altered by this change.
No existing FSAR accident analyses are affected. i I
_,,,,,,,.---~_z.
(228)
Description of Change This change involved installing low level switches on all MSIV and FWIV hydraulic oil reservoirs.
The change affected drawings 13-E-ZCC-046 and 13-E-ZJC-006, which are incorporated into the FSAR by reference.
This change was implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation This change was made to ensure that the MSIVs and FWIVs would be able to perform their function.
No existing FSAR safety analyses are affected.
(229)
Description of Change This change involved reviewing control room light circuits to provide isolation of the control room lights to prevent loss of all valve indication in the event of a control room fire.
The change affected drawing 13-E-SIB-014, which is incorporated into the FSAR-by reference.
This change was implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation This change allows the circuits to function per the design intent, and increases safety by insuring the control room circuitry can be isolated in the event of a fire.
(230)
Description of Change This change involved inserting a needle valve into the pressure sensing line of the blowdown demineralizer system to serve as a snubber.
In addition, a pressure indicator was installed. The change affected FSAR Figure 10.4-5 and was implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation This change was made to smooth out the pressure fluctuation la the sensing line and eliminate erratic cycling on flows of 50 gpm or less. The change did not affect any existing FSAR accident analyses.
(231)
Description of Change A passive backflush path was installed to direct any potential reactor drain tank backflush water away frora the reactor coolant pump seal housing and to a floor drain. This change affceted FSAR Figure 9.3-13 and was implemented in PVNGS Unit 2 during this reporting period....
Summary of Safety Evaluation The addition of this modification prevents flushing of the reactor coolant pump seal housings and other pump components with water backing up from the vapor seal leak-off line.
The flushing of these components could result in damage to some pump components when exposed to the borated water. Thus, this change gives a safety improvement by preventing potential component degradations.
(232)
Description of Change A one inch manual islation valve was added in the reactor coolant gas vent system.
This modification affected FSAR Figure 5.1-1 and was implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation The addition of the manual isolation valve will ensure the isolability of the reactor coolant gas vent system when necessary.
The additional valve does not change the function of the system since the valve will be left in the locked open position during normal operations.
(233)
Description of Change This modification installed fiber optic data links between the Core Monitoring Computer and the Core Protection Calculator channels.
The change affected drawing 13-E-ZJC-007 which is incorporated by reference into the FSAR and was completed in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation The fiber optic data link provides for the automatic transfer of data from the Core Protection Calculators / Control Element Assembly Calculators to the Core Monitoring Computer for review and evaluation in the unlikely event of a plant accident or abnormal operating condition.
The fiber optic interface between the computer systems will not alter the safety of the plant or reduce the margin of safety.
(234)
Description of Change For the vibration and loose parts monitoring system, the existing single annunciator and computer alarm was separated into three alarms.
This change affected drawing 13-E-ZJC-009 which is incorporated by reference into the FSAR.
The modification was completed in PVNGS Unit 2 dtiring this reporting period.. _
Summary of Safety Evaluation The change, to separate the existing single vibration and loose parts alarm into three alarms, will allow the control room operators to better diagnose and react to alarms from the vibration and loose parts monitoring system.
This change does not change equipment in a way which would increase the probability of occurrence or consequences of accidents.
The change allows for more alarms to inform the operator of system problems.
(235)
Description of Change This facility change involved the installation and wiring of equipment associated with the Chemical and Radiological Analysis Computer System (CRACS) including the Post Accident Sampling System (PASS) control console. Also, contacts for effluent flow rate data for each release point are provided to CRACS.
These modifications affected several electrical diagrams and auxiliary building conduit and tray plan drawings which are incorporated by reference into the FSAR.
The change was completed in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation These changes to the CRACS system will enable CRACS to operate as intended. The CRACS system is not a safety related system, nor is it required for safe shutdown of the facility.
The system is used only for post-accident monitoring.
(236)
Description of Change In support of the Unit 2 low power physics testing, the excore neutron flux monitoring system control channels were disconnected from the startup/ control channel drawer and routed to the reactivity computer.
This affected CESSAR Section 7.7.1.1.9 and was implemented in PVNGS Unit 2 during this reporting period.
Summary of Safety Evaluation CESSAR Section 7.7.1.1.9 states that the excore neutron flux monitoring system control channels provide neutron flux information to the Reactor Regulating System (RRS) in the power operating range of 1 to 125% power.
In order to support Unit 2 low power physics testing, it was necessary to disconnect the control channel input to the RRS so that the reactivity computer could be used.
This cange had no affect on plant safety since the RRS is only operated in manual below 15%
reactor power as stated in CESSAR 7.7.1.1.1.
(237)
Description of Change Test procedures 73PE-2SB01 and 73PE-2SD01 were developed to verify the operation of the QSPDS-ERFDADS fiber optic data link and to correlate the ERFDADS field data with the plant instrumentation.
These two tests are tests that are not presently described in the FSAR. - -
Summary of Safety Evaluation The test of the QSPDS-ERFDADS data link is a functional test for the system which will have no affect on the safety of the plant.
The test to collect ERFDADS field data does not perform any perturbation to the plant and the existing FSAR analysis covers all probable accidents.
(238)
Description of Change A new test procedure was initiated to determine the steam generator blowdown flowrates for use in the COLSS computer system.
This new test is not currently described in the FSAR for PVNGS.
Summary of Safety Evaluation The FSAR does nct describe a test to measure blowdown flow rates or determine the appropriate COLSS constants.
The COLSS uses a blowdown flow rate in its calculation of reactor power.
This test procedure is performed to determine appropriate constants for use in COLSS.
Therefore, the test will serve to lower the inaccuracy in the COLSS reactor power calculation associated with blowdown flow rates.
Additionally, since the blowdown system will remain in accordance with design and serves no s.afety function, the probability of occurrence of an accident or malfunction previously analyzed will not be increased.
(239)
Description of Change The test procedure for the natural circulation test described in CESSAR 14.2.12.5.1 was changed to coordinate the performance of a turbine trip test in conjunction with the natural circulation test.
This test procedure change involved a change to a procedure described in the FSAR.
Summary of Safety Evaluation i
The natural circulation test is based on the total loss of coolant flow analys's of CESSAR 15.3.1 which assumes a total loss of flow at 100% power kroducing a reactor trip on low DNBR.
The change to this test proced{re describes a test incorporating a total loss of flow approximate 1f 5-10 minutes following the turbine / reactor trip from 100% power (turbine trip is analyzed in CESSAR 15.2.2).
The test will be performed in a manner conservative with respect to the analyses and thus, will *not increase the probability or consequences of any previously analyzed accidents.
(240)
Description of Change In support of the PVNGS Unit 2 power ascension testing program, procedures were written to perform RCS flow measurements at the 20%,
50%, 80%, and 100% power plateaus.
These new procedures were tests that are not currently described in the FSAR.
4
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m Summary of Safety Evaluation These procedures are not described in the FSAR but they are described in the startup test requirements document for the COLSS system.
The test procedures at each power plateau require only steady-state data acquisition and calibration of RCS flow and thermal power.
The performance of these test procedures will enhance safety by verifying the safety analysis assumptions regarding power and flow.
(241)
Description of Change For PVNGS Units 1 and 2, new procedures were written for the operation and testing of the Steam Bypass Control System (SBCS).
The procedure involves a test not described in the FSAR.
Summary of Safety Evaluation The SBCS is a non-safety related system.
The cycling (testing) of a SBCS valve that has been isolated from the secondary system is not specifically described in the FSAR. However, the plant is designed to permit this testing.
Isolation of cne SBCS valve for testing does not compromise the safety analysis assumptions since CESSAR Table 15.0-6 lists the failure of an SBCS valve as one of the analyzed failures and the accident analyses of sections 15.2.1 through 15.2.3 assume no automatic or manual functioning of these valves.
(242)
Description of Change A new test procedure was written to allow for the investigation of the integrated performance of the condensate, feedwater, and extraction steam systems.
This procedure involves a test not described in the FSAR.
Summary of Safety Evaluation The new test procedure collects plant performance data over a range of operating conditions of the condensate, feedwater, and extraction steam systems.
Four test cases are investigated.
The test cases involve different combinations of the number of condensate pumps
- running, power level, and whether the heater drain tanks are cross-connected or not.
The tests do not introduce any unanalyzed operating configuration to the secondary systems.
(243)
Description of Change A
procedure change was initiated to the systems chemistry specifications procedure.
This change affected the FSAR section concerning the chemistry specification for the essential cooling water system. _
Summary of Safety Evaluation The existing FSAR Section 9.2.2 concerning the essential cooling water system describes a chromate based corrosion inhibitor.
Due to environmental and regulatory concerns, this inhibitor is not in use at PVNGS and a vendor recommended inhibitor is used instead of the chromate based inhibitor.
All chemistry limits for this system are within applicable vendor and industry recommendations.
(244)
Description of Change For the PVNGS Unit 2 post-core hot functional chemistry test, a new procedure was written to perform this test.
This new test procedure involved a change to procedures as described in the FSAR.
Summary of Safety Evaluation CESSAR Section 14.2.12.3.5 lists acceptance criteria for the post-core hot functional chemistry as "RCS and steam generator chemistry can be maintained as described in Sections 9.3.4 and 10.3.4."
These referenced sections are out of date and have been superceded by an ANPP letter to the NRC (ANPP-31502).
The new chemistry limits established by this letter have been approved by the NRC in a supplement to their safety evaluation report.
(245)
Description of Change A procedure change was implemented to the radiation protection alarm setpoint determination procedure to correct the range for channel 2 of radiation monitors RU-142, 144, and 146.
This procedure change affected Table 11.5-1 of the FSAR.
Summary of Safety Evaluation This change to the range of the subject radiation monitors was evaluated by an engineering evaluation and the evaluation determined that the monitors are able to meet their design basis.
(246)
Description of Change In support of the PVNGS Unit 2 power ascension testing program, new procedures were written for the adjustment of the COLSS secondary pressure loss terms at the 20%, 50%, 80%, and 100% power plateaus.
These procedures (one for each power level) represent tests not described in the FSAR.
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Summary of Safety Evaluation These test procedures provide the methods used to ensure that the COLSS secondary calorfmetric algorithm gives acceptable agreement between the measured and calculated values for feedwater and steam generator pressures.
These procedures are not described in the FSAR but they are described in the startup test requirements document for the COLSS system.
The performance of the procedures ensure the accuracy of the COLSS secondary power calculations and do not involve an unreviewed safety question.
(247)
Description of Change A temporary procedure was written to perform a lithium tracer test on a steam generator. This test is not described in the FSAR.
Summary of Safety Evaluation The test involves the installation of a temporary chemical injection pump at drain valves SGE-V608 and SGE-V644.
The steam generator flow tracer test involves the use of small quantities of lithium hydroxide.
The addition of the lithium hydroxide to the secondary systea will have no effect on the steam gettrator materials.
Only trace amounts of lithium hydroxide are used and this will not result in appreciable concentrations in a sludge pile or tube / support crevice region.
(248)
Description of Change A temporary procedure was written to allow verification of tritium release flow rates from the boric acid concentrator distillate release point at different atmospheric conditions.
Summary of Safety Evaluation The procedure allows for the monitoring of the release flow path from the boric acid concentrator distillate release point.
Clear plastic covers are installed in the ductwork to allow for visuel observations.
Additionally, temperature and humidity readings are taken in the ventilation line.
This allows for monitoring the boric acid concentrator operation at various atmospheric conditions.
(249)
Description of Change In support of the PVNGS Unit 2 power ascension testing program, a 4,
procedure was written to allow for the initialization of the COLSS system at 0% power. This is a test that is not described in the FSAR.
Summary of Safety Evaluation This test is a verification that proper values have been input to the J
COLSS system during the post-core hot functional testing phase and in involves only steady-state data collection.
The test does not involve an unrevfewed safety question. 1
-= _ _. _ -.
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(250)
Description of Change Surveillance test procedure 36ST-9SA02 was revised to change the test method to avoid cycling control room essential isolation dampers HJB-M56 and M57.
This revision to a change to a procedure described in the FSAR.
Summary of Safety Evaluation The reviewed surveillance test procedure will only test the subgroup relay actuation as opposed to the previous method of verifying the component actuation for dampers HJB-M56 and M57.
The probability or consequences of accidents are not increased by this change since these dampers are administratively maintained closed (their actuated position) and there is no chance for a loss of control room isolation via these two dampers.
(251)
Description of Change The plant annunciator system was modified to incorporate various human factors review findings.
These modifications affected various electrical drawings that are incorporated by reference into the FSAR.
The modifications were completed in PVNGS Unit 1 during this reporting period.
Summary of Safety Evaluation These changes to the plant annunciator system were accomplished under DCP 1SJ-RK-005. The changes were made to resolve human factors review findings and improve the safety of the plant by improving the human factors interface between the operators and the plant annunciator system.
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